1
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
(Dr Vincenzo Peluso ndash ENEA)
2
1 INTRODUCTION
bull ERANOS 21 is a system of neutron and gamma codes developed within a European framework
bull This system meets the needs expressed by the industrialists and the teams working on the design of fast reactors present and future
bull It allows moreover with the use of the convivial LU userrsquos language to perform programs of RampD in reactor physics without systematically needing specific developments
3
2 ERANOS FUNCTIONS
bull Fast reactor core shielding and fuel cycle calculations can be performed with the ERANOS system ERANOS is a deterministic code system so neutron physics calculations are performed at the celllattice level and at the core level
bull The celllattice code ECCO (European Cell COde) is fed by libraries that are in a direct access format in various energy meshes 1968 groups (all-purpose) 175 groups (shielding purposes) the 172-group XMAS scheme (refined in the low energy range) and 33 groups (energy mesh generally used for core calculations)
bull Four sets of libraries can be used JEF-22 obtained directly from JEF22 evaluations ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on
integral experiments JEFF-31 obtained directly from JEFF31 evaluations ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
NB The Code HETAIRE and the library CARNAVAL4 of the old Fast Neutron CEA code system are also available in ERANOS 21 For neutron shielding and gamma propagation and heating applications the PROPANE and VASCO libraries are also available
4
2 ERANOS FUNCTIONS
bull The ECCO code solves the resonant nuclide self-shielding using the sub-group method and computing with a collision probability method a fine-group solution of the transport integral equation The cross-sections can be condensed and homogenized
bull ECCO can model the following geometries Plane Cylindrical 2D rectangular sub-assembly with or without wrapper2D hexagonal sub-assembly with or without wrapper 3D slab geometry useful to model platelet fuel
bull The core calculations carried out by ERANOS include reactivity flux spatial power distribution reactivity coefficients burnup and control rod worth Moreover for very different applications (analysis of experiments reactivity coefficients follow-up and management of core loadings) traditional generalized and harmonics perturbation modules are available
5
2 ERANOS FUNCTIONS
bull The ERANOS code system is a very open system modular whose objects (SET or EDL) are easy to handle by many modules and the LU user language This makes possible using the various available modules to create procedures for specific types of applications eg to define separately design and reference calculations schemes for respectively scoping and detailed calculations
bull Calculations performed by ERANOS are gathered according to the following chapters
Operating Conditions Internal Transfer of nuclear dataRelease of energy and damage to the structures Diffusion modules 1D 2D (XY RZ and Hexagonal) 3D Hexagonal Z Sn transport modules 1D 2D (XY and RZ ) Nodal diffusion and transport modules P1 P3 P5 SP3 SP5 (XY XYZ
Hexagonal and Hexagonal Z)Perturbation modules Burn-up modules
6
3 The ALOS system
Whatrsquos ALOS
bullThe ALOS software provides a complete development environment
bullIt includes
-a programming language =gt ESOPE -basic data structures =gt the SEGMENTs the EDLs (or SETs ) -an utility library to manage memory =gtGEMAT -a user command language =gtLU -an archiving utility =gtARCHIVE -a relational data base management system =gt SGBD
7
31 LU language
LU is the user language for all software developed under ALOS
It allowsbullTo handle the variables(integers reals strings of characters pointershellip)
and the SETsbullTo call up a program(ESOPE standard FORTRAN C hellip)bullTo perform numericaland logical calculationsusing basic mathematical
functions SIN COS LOG EXP hellipbullTo make advanced programmingusing loops (POUR TANTQUE) or
conditional execution structures (SI hellip SINONSI hellip SINON hellip FINSI)bullTo encapsulate complex sequenceof instructions in macro instructions
called PROCEDUREbullTo use archiving utilitiesand the internal relational SGBD
8
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
9
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
2
1 INTRODUCTION
bull ERANOS 21 is a system of neutron and gamma codes developed within a European framework
bull This system meets the needs expressed by the industrialists and the teams working on the design of fast reactors present and future
bull It allows moreover with the use of the convivial LU userrsquos language to perform programs of RampD in reactor physics without systematically needing specific developments
3
2 ERANOS FUNCTIONS
bull Fast reactor core shielding and fuel cycle calculations can be performed with the ERANOS system ERANOS is a deterministic code system so neutron physics calculations are performed at the celllattice level and at the core level
bull The celllattice code ECCO (European Cell COde) is fed by libraries that are in a direct access format in various energy meshes 1968 groups (all-purpose) 175 groups (shielding purposes) the 172-group XMAS scheme (refined in the low energy range) and 33 groups (energy mesh generally used for core calculations)
bull Four sets of libraries can be used JEF-22 obtained directly from JEF22 evaluations ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on
integral experiments JEFF-31 obtained directly from JEFF31 evaluations ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
NB The Code HETAIRE and the library CARNAVAL4 of the old Fast Neutron CEA code system are also available in ERANOS 21 For neutron shielding and gamma propagation and heating applications the PROPANE and VASCO libraries are also available
4
2 ERANOS FUNCTIONS
bull The ECCO code solves the resonant nuclide self-shielding using the sub-group method and computing with a collision probability method a fine-group solution of the transport integral equation The cross-sections can be condensed and homogenized
bull ECCO can model the following geometries Plane Cylindrical 2D rectangular sub-assembly with or without wrapper2D hexagonal sub-assembly with or without wrapper 3D slab geometry useful to model platelet fuel
bull The core calculations carried out by ERANOS include reactivity flux spatial power distribution reactivity coefficients burnup and control rod worth Moreover for very different applications (analysis of experiments reactivity coefficients follow-up and management of core loadings) traditional generalized and harmonics perturbation modules are available
5
2 ERANOS FUNCTIONS
bull The ERANOS code system is a very open system modular whose objects (SET or EDL) are easy to handle by many modules and the LU user language This makes possible using the various available modules to create procedures for specific types of applications eg to define separately design and reference calculations schemes for respectively scoping and detailed calculations
bull Calculations performed by ERANOS are gathered according to the following chapters
Operating Conditions Internal Transfer of nuclear dataRelease of energy and damage to the structures Diffusion modules 1D 2D (XY RZ and Hexagonal) 3D Hexagonal Z Sn transport modules 1D 2D (XY and RZ ) Nodal diffusion and transport modules P1 P3 P5 SP3 SP5 (XY XYZ
Hexagonal and Hexagonal Z)Perturbation modules Burn-up modules
6
3 The ALOS system
Whatrsquos ALOS
bullThe ALOS software provides a complete development environment
bullIt includes
-a programming language =gt ESOPE -basic data structures =gt the SEGMENTs the EDLs (or SETs ) -an utility library to manage memory =gtGEMAT -a user command language =gtLU -an archiving utility =gtARCHIVE -a relational data base management system =gt SGBD
7
31 LU language
LU is the user language for all software developed under ALOS
It allowsbullTo handle the variables(integers reals strings of characters pointershellip)
and the SETsbullTo call up a program(ESOPE standard FORTRAN C hellip)bullTo perform numericaland logical calculationsusing basic mathematical
functions SIN COS LOG EXP hellipbullTo make advanced programmingusing loops (POUR TANTQUE) or
conditional execution structures (SI hellip SINONSI hellip SINON hellip FINSI)bullTo encapsulate complex sequenceof instructions in macro instructions
called PROCEDUREbullTo use archiving utilitiesand the internal relational SGBD
8
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
9
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
3
2 ERANOS FUNCTIONS
bull Fast reactor core shielding and fuel cycle calculations can be performed with the ERANOS system ERANOS is a deterministic code system so neutron physics calculations are performed at the celllattice level and at the core level
bull The celllattice code ECCO (European Cell COde) is fed by libraries that are in a direct access format in various energy meshes 1968 groups (all-purpose) 175 groups (shielding purposes) the 172-group XMAS scheme (refined in the low energy range) and 33 groups (energy mesh generally used for core calculations)
bull Four sets of libraries can be used JEF-22 obtained directly from JEF22 evaluations ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on
integral experiments JEFF-31 obtained directly from JEFF31 evaluations ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
NB The Code HETAIRE and the library CARNAVAL4 of the old Fast Neutron CEA code system are also available in ERANOS 21 For neutron shielding and gamma propagation and heating applications the PROPANE and VASCO libraries are also available
4
2 ERANOS FUNCTIONS
bull The ECCO code solves the resonant nuclide self-shielding using the sub-group method and computing with a collision probability method a fine-group solution of the transport integral equation The cross-sections can be condensed and homogenized
bull ECCO can model the following geometries Plane Cylindrical 2D rectangular sub-assembly with or without wrapper2D hexagonal sub-assembly with or without wrapper 3D slab geometry useful to model platelet fuel
bull The core calculations carried out by ERANOS include reactivity flux spatial power distribution reactivity coefficients burnup and control rod worth Moreover for very different applications (analysis of experiments reactivity coefficients follow-up and management of core loadings) traditional generalized and harmonics perturbation modules are available
5
2 ERANOS FUNCTIONS
bull The ERANOS code system is a very open system modular whose objects (SET or EDL) are easy to handle by many modules and the LU user language This makes possible using the various available modules to create procedures for specific types of applications eg to define separately design and reference calculations schemes for respectively scoping and detailed calculations
bull Calculations performed by ERANOS are gathered according to the following chapters
Operating Conditions Internal Transfer of nuclear dataRelease of energy and damage to the structures Diffusion modules 1D 2D (XY RZ and Hexagonal) 3D Hexagonal Z Sn transport modules 1D 2D (XY and RZ ) Nodal diffusion and transport modules P1 P3 P5 SP3 SP5 (XY XYZ
Hexagonal and Hexagonal Z)Perturbation modules Burn-up modules
6
3 The ALOS system
Whatrsquos ALOS
bullThe ALOS software provides a complete development environment
bullIt includes
-a programming language =gt ESOPE -basic data structures =gt the SEGMENTs the EDLs (or SETs ) -an utility library to manage memory =gtGEMAT -a user command language =gtLU -an archiving utility =gtARCHIVE -a relational data base management system =gt SGBD
7
31 LU language
LU is the user language for all software developed under ALOS
It allowsbullTo handle the variables(integers reals strings of characters pointershellip)
and the SETsbullTo call up a program(ESOPE standard FORTRAN C hellip)bullTo perform numericaland logical calculationsusing basic mathematical
functions SIN COS LOG EXP hellipbullTo make advanced programmingusing loops (POUR TANTQUE) or
conditional execution structures (SI hellip SINONSI hellip SINON hellip FINSI)bullTo encapsulate complex sequenceof instructions in macro instructions
called PROCEDUREbullTo use archiving utilitiesand the internal relational SGBD
8
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
9
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
4
2 ERANOS FUNCTIONS
bull The ECCO code solves the resonant nuclide self-shielding using the sub-group method and computing with a collision probability method a fine-group solution of the transport integral equation The cross-sections can be condensed and homogenized
bull ECCO can model the following geometries Plane Cylindrical 2D rectangular sub-assembly with or without wrapper2D hexagonal sub-assembly with or without wrapper 3D slab geometry useful to model platelet fuel
bull The core calculations carried out by ERANOS include reactivity flux spatial power distribution reactivity coefficients burnup and control rod worth Moreover for very different applications (analysis of experiments reactivity coefficients follow-up and management of core loadings) traditional generalized and harmonics perturbation modules are available
5
2 ERANOS FUNCTIONS
bull The ERANOS code system is a very open system modular whose objects (SET or EDL) are easy to handle by many modules and the LU user language This makes possible using the various available modules to create procedures for specific types of applications eg to define separately design and reference calculations schemes for respectively scoping and detailed calculations
bull Calculations performed by ERANOS are gathered according to the following chapters
Operating Conditions Internal Transfer of nuclear dataRelease of energy and damage to the structures Diffusion modules 1D 2D (XY RZ and Hexagonal) 3D Hexagonal Z Sn transport modules 1D 2D (XY and RZ ) Nodal diffusion and transport modules P1 P3 P5 SP3 SP5 (XY XYZ
Hexagonal and Hexagonal Z)Perturbation modules Burn-up modules
6
3 The ALOS system
Whatrsquos ALOS
bullThe ALOS software provides a complete development environment
bullIt includes
-a programming language =gt ESOPE -basic data structures =gt the SEGMENTs the EDLs (or SETs ) -an utility library to manage memory =gtGEMAT -a user command language =gtLU -an archiving utility =gtARCHIVE -a relational data base management system =gt SGBD
7
31 LU language
LU is the user language for all software developed under ALOS
It allowsbullTo handle the variables(integers reals strings of characters pointershellip)
and the SETsbullTo call up a program(ESOPE standard FORTRAN C hellip)bullTo perform numericaland logical calculationsusing basic mathematical
functions SIN COS LOG EXP hellipbullTo make advanced programmingusing loops (POUR TANTQUE) or
conditional execution structures (SI hellip SINONSI hellip SINON hellip FINSI)bullTo encapsulate complex sequenceof instructions in macro instructions
called PROCEDUREbullTo use archiving utilitiesand the internal relational SGBD
8
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
9
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
5
2 ERANOS FUNCTIONS
bull The ERANOS code system is a very open system modular whose objects (SET or EDL) are easy to handle by many modules and the LU user language This makes possible using the various available modules to create procedures for specific types of applications eg to define separately design and reference calculations schemes for respectively scoping and detailed calculations
bull Calculations performed by ERANOS are gathered according to the following chapters
Operating Conditions Internal Transfer of nuclear dataRelease of energy and damage to the structures Diffusion modules 1D 2D (XY RZ and Hexagonal) 3D Hexagonal Z Sn transport modules 1D 2D (XY and RZ ) Nodal diffusion and transport modules P1 P3 P5 SP3 SP5 (XY XYZ
Hexagonal and Hexagonal Z)Perturbation modules Burn-up modules
6
3 The ALOS system
Whatrsquos ALOS
bullThe ALOS software provides a complete development environment
bullIt includes
-a programming language =gt ESOPE -basic data structures =gt the SEGMENTs the EDLs (or SETs ) -an utility library to manage memory =gtGEMAT -a user command language =gtLU -an archiving utility =gtARCHIVE -a relational data base management system =gt SGBD
7
31 LU language
LU is the user language for all software developed under ALOS
It allowsbullTo handle the variables(integers reals strings of characters pointershellip)
and the SETsbullTo call up a program(ESOPE standard FORTRAN C hellip)bullTo perform numericaland logical calculationsusing basic mathematical
functions SIN COS LOG EXP hellipbullTo make advanced programmingusing loops (POUR TANTQUE) or
conditional execution structures (SI hellip SINONSI hellip SINON hellip FINSI)bullTo encapsulate complex sequenceof instructions in macro instructions
called PROCEDUREbullTo use archiving utilitiesand the internal relational SGBD
8
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
9
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
6
3 The ALOS system
Whatrsquos ALOS
bullThe ALOS software provides a complete development environment
bullIt includes
-a programming language =gt ESOPE -basic data structures =gt the SEGMENTs the EDLs (or SETs ) -an utility library to manage memory =gtGEMAT -a user command language =gtLU -an archiving utility =gtARCHIVE -a relational data base management system =gt SGBD
7
31 LU language
LU is the user language for all software developed under ALOS
It allowsbullTo handle the variables(integers reals strings of characters pointershellip)
and the SETsbullTo call up a program(ESOPE standard FORTRAN C hellip)bullTo perform numericaland logical calculationsusing basic mathematical
functions SIN COS LOG EXP hellipbullTo make advanced programmingusing loops (POUR TANTQUE) or
conditional execution structures (SI hellip SINONSI hellip SINON hellip FINSI)bullTo encapsulate complex sequenceof instructions in macro instructions
called PROCEDUREbullTo use archiving utilitiesand the internal relational SGBD
8
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
9
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
7
31 LU language
LU is the user language for all software developed under ALOS
It allowsbullTo handle the variables(integers reals strings of characters pointershellip)
and the SETsbullTo call up a program(ESOPE standard FORTRAN C hellip)bullTo perform numericaland logical calculationsusing basic mathematical
functions SIN COS LOG EXP hellipbullTo make advanced programmingusing loops (POUR TANTQUE) or
conditional execution structures (SI hellip SINONSI hellip SINON hellip FINSI)bullTo encapsulate complex sequenceof instructions in macro instructions
called PROCEDUREbullTo use archiving utilitiesand the internal relational SGBD
8
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
9
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
8
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
9
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
9
32 Basic LU
Each term of a LU instruction may be one of the following types
-numeric constant ==gt 10 -5 125789E-05-text constant ==gt Martinlsquo A= Resultat-keywords ==gt ITERATIONS_EXTERNES-result variable ==gt -gtX -gt SIGMA-input variable ==gt (X) (SIGMA)-expression ==gt (X+1) (SIGMASIGMA)
bullA LU instruction can stand on several lines
bullThe last instruction of a LU program is FIN
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
10
32 Basic LU
bull A LU instruction endswith
bull Only 80 first characters are valid on a line
bull A string of characters must not increase more than 500 characters
bull The text that follows an exclamation mark () is ignored (a line that begins with is a comment)
bull Lower cases and upper cases are equivalentexcept in text variable
bull Tabulations are prohibited
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
11
33 Arithmetic and logical calculation
bullBasic operators
+ for the addition- for the subtraction for the division for the multiplication for the power
bull Comparison operators
= equal lt lesser thangt greater than= different fromlt= lesser or equalgt= greater or equal
bullLogical operators
ET ANDOU ORNON NOT
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
12
33 Arithmetic and logical calculation
bull We also use the functions SIN COS TAN ASIN ATAN ACOS EXP LOG LOG10ABSENT MODMAXMIN SOMME PRODUIT TRI
bull The sequence -gtTAB 7 2 5 4 3 6 1 -gtSUM SOMME (TAB)
-gtPROD PRODUIT (TAB) -gtI TRI(TAB) -gtJ TAB(TRI(TAB))
provides-gtSUM 28-gtPROD 5040-gtI 7 2 5 4 3 6 1-gtJ 1 2 3 4 5 6 7
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
13
34 Others functions
bull REP operator
The sequence-gtA REP(6)-gtB REP(-6)-gtC REP(3toto)
is similar to-gtA 1 2 3 4 5 6 -gtB 6 5 4 3 2 1 -gtC totolsquo lsquototorsquolsquototorsquo
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
14
35 The printing utility
bull Printing a variable with the operator -gtT 1 4 2E-02 78 T
provides -gtT 1 4 200000E-02 78
2 Tprovides -gtT 1 4
200000E-02 78
-1 Tprovides -gtT
(1) 1(2) 4(3) 200000E-02(4) 78
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
15
36 Utilities
bull Remove a variable X
bull Remove an EDL (EDL_MACRO)
bull Duplication of a variable and a SET
= -gt Y X the variable X is duplicated under a new Reference Y
= -gtNEW_EDL (EDL_MACRO) the set pointed by the variable MACRO_SET isduplicated
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
16
37 The POUR (FOR) loop
bull This structure can be used only in a procedure Syntax
-gtCONTROL_ROD_POSITION 0 100 200 400POUR-gtIP 1 2 3 4
GEOMETRY_MODIFICATION-gt NEW_GEOMETRY_SETGEOMETRY(GEOMETRY_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 19 18 (CONTROL_ROD_POSITION(IP))POSITION 23 19 (CONTROL_ROD_POSITION(IP))POSITION 13 23 (CONTROL_ROD_POSITION(IP))
FLUX_CALCULATION-gt NEW_FLUX_SET -gtEIGENVALUENEW_GEOMETRY_SET (NEW_GEOMETRY_SET) (NEW_FLUX_SET)
FINPOUR
The instructions between POUR and FINPOUR will be executed 4 timesThe variable IP successively takes the values 1 2 3 and 4
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
17
38 The TANTQUE (WHILST) loop
bull This structure can be used only in a procedure
-gtZ_AXIS 0 100 200 400 -gtIP 1 TANTQUE (IP lt= Z_AXIS() )
GEOMETRY_MODIFICATION -gtNEW_GEOMETRY_SET
GEOMETRY(GEOMETRIE_SET)CORE(CORE_SET)MEDIUM(MEDIUM_SET)NEW_Z_AXISPOSITION 1918 (Z_AXIS(IP))POSITION 2319 (Z_AXIS(IP))POSITION 1823
(Z_AXIS(IP))
FLUX_CALCULATION -gtNEW_FLUX_SET -gtEIGENVALUE
NEW_GEOMETRY_SETNEW_MACRO_SET (NEW_GEOMETRY_SET)
(NEW_FLUX_SET)-gtIP (IP+1)
FINTANTQUE
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
18
39 Conditional Conditional execution execution The SI (IF) structure
bull This structure can be used only in a procedure
SI (GEOMETRY_TYPE=lsquoXYrsquo) XY caseXY_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoH2Drsquo) H2D caseH2D_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoRZrsquo) RZ caseRZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINONSI (GEOMETRY_TYPE=lsquoXYZrsquo) XYZ caseXYZ_GEOMETRY_CREATION -gtEDL_GEOMETRYhellip
SINON H3D caseFINSI
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
19
310 The PROCEDURES
bull A procedure allows to encapsulate a sequence of LU instructions
bull A procedure is similar to a function
bull A procedure is a particular SET (SET of type PROCEDURE V1)
bull A procedure may be store on a permanent file (ARCHIVE file)
1048708Structure of a procedure
PROCEDURE-gtprocedure_name
input1 input2 hellipinputn
-gtoutput1 hellip -gtoutputn Sequence of LU instructions
FINPROC
Input and output arguments can be listedin the order you want
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
20
310 The PROCEDURES
bull Example (a way to create an EDL_MACRO with micro cross sections)
PROCEDURE-gtCREATE_MACRO_SAMPLE EDL_MICRO EDL_MILIEU-gtEDL_MACRO_SAMPLE
isotopeconc_isoreaction
SI (CONC_ISO()=0) -gtCONCENTRATION CONCENTRATION (CONC_ISO) FINSI
CALCUL_MACRO -gtEDL_MACRO_SAMPLEMICRO (EDL_MICRO)MILIEU (EDL_MILIEU)(CONCENTRATION)SECTION (reaction)PAR_ECHANTILLON (isotope) (isotope)
FINPROC
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
21
310 The PROCEDURES
bull Call a procedure
ARCHIVE lsquoARFILErsquo -gtEDL_MILIEU MILIEU SPX 180 ARCHIVE lsquoARFILErsquo -gtEDL_MICRO MICRO SPX 180
-gtISOTOPE lsquoU235rsquo -gtCONC_ISO 1 -gtREACTION lsquoFISSIONrsquo
The way below to call the procedure is also valid since the names of the variables are similar to those used when the procedure has been created
CREATE_MACRO_SAMPLE
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
22
311 The ARCHIVE utility
bull It allows
-to create a file with his name and its initial spaceARCHIVE lsquofile_namersquo INITIALISER nb-blocs long-blocs
-to store set in a file with binary formatARCHIVE lsquofile_namersquo ltlt REMPLACERgtgt (FLUX_SET) FLUX TGV ERANOS
-to get back a set previously stored ARCHIVElsquofile_namersquo -gtFLUX _SET FLUX TGV ERANOS
-to suppress a set previously storedARCHIVE lsquofile_namersquo SUPPRIMER FLUX TGV ERANOS
-to print the list of the set stored in a fileARCHIVE lsquofile_namersquo CATALOGUE
-to store this list and then utilize itARCHIVElsquofile_namersquoCATALOGUE -gtCATAL_SETEDL_NOM (CATAL_SET) -gtSET_NAME
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
23
312 The PARAM file
bull The way in which the GEMAT data management scheme works depends of memory parameters These parameters must be placed in an ASCII file named PARAM
bull This file is mandatory in the execution environment and contains
ESOPE=nb-wordsNTRK=nb-blocksLTRK=size-blocks
nb-words number of words which allows to allocate the workspace in RAM memory needed by the job( 1 word = 4 or 8 bytes depending of the computer)This size cannot exceed the memory space of the microprocessor
nb-blocks number of blocks of the overflow filesize-blocks size of a block
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
24
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ------3500000 ALLOCATION MEMOIRE INSUFFISANTEGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT DONT 0 MOTS LIBRES EN ZONE DYNAMIQUE ET 0 MOTS LIBRES EN ZONE FIXE
bull CAUSES1The ESOPE parameter is too large2The ESOPE parameter has not been defined
bull REMEDY1Decrease the value of ESOPE2Assign a value to ESOPE
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
25
313 The GEMAT errors
bull MESSAGE
---GEMAT ERROR ---SUBROUTINE NCMAC ---INSTRUCTION 91 ---SEGINI ZAUX2 ---PAS ASSEZ DE PLACE EN MEMOIREGEMAT 94 (FEV 93) DUMP DE LA MEMOIRE GEREE PAR GEMAT
bull CAUSESThe program complains that there is not enough memory space for the calculation it has been asked to perform
bull REMEDYIncrease the value of ESOPE
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
26
4 The multi-group and multi-temperature LIBRARIES
bull Four sets of libraries can be used
JEF-22 obtained directly from JEF22 evaluations
ERALIB1 obtained from the JEF-22 libraries by a statistical fitting on integral experiments
JEFF-31 obtained directly from JEFF31 evaluations
ENDFB-VI8 obtained directly from ENDFB-VI8 evaluations
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
27
41 JECCOLIB2 amp ERALIB1
bullThe data are mainly coming from JEF2 evaluations except for ERALIB1 libraries which contain ajusted nuclear data values (elastic inelastic capture nXn fissionhellip) for the main nuclei
235 238U 239 240 241 242Pu Zr Gd Al 56Fe 58Ni 52Cr Na O C 10B bdH (H from H2O)
bullThere are 3 libraries with various group weighting (structure and flux)
the 1st one contains 41 isotopes (1968 groups) it is used for reference calculations in any kind of application
the 2nd one contains 287 isotopes (172 groups) it is used for design calculations in thermal spectra
the 3rd one contains 287 isotopes (33 groups) it is used for design calculations in fast spectra
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
28
ASPILIB2P
The data are mainly coming from JEF2 evaluations The library contains 58 isotopes (175 groups VITAMIN-J group structure) Angular distributions for structural materials cross-sections are more detailed than in other libraries It is used for
shielding calculations
DPA (Displacement Per Atom) The values stored are doses for every reaction capture fission elastic inelastic There are 3 ASCII libraries (33 172 and 175 groups) each of them containing 13
isotopes (iron chromium and nickel elements) There are used for structural damage calculations
KERMA (Kinetic Energy Release in MAterials) The values stored are total (ie neutron + gamma) and for every reaction (capture
fission elastic inelastic) There are 2 libraries (in ASCII format)
KERMA33 contains 52 isotopes (33 groups) KERMA175 contains 40 isotopes (175 groups)
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
29
The following table indicates whether the energy boundaries of the different structure allow a condensation from one to another
Structure1968 175 172 33 15
1968 -- yes yes yes yes
175 -- -- no no no
172 -- -- -- yes yes
33 -- -- -- -- yes
15 -- -- -- -- --
Energy limits of the different structures (15 groups are used for sensitivity studies)
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
30
NB OF GROUPS 1968 175 172 33UPPER E (eV)
1964033E+07 1 1 1 1 1 1947734E+07 2 1 1 1 1 1931570E+07 3 1 1 1 1 1915541E+07 4 1 1 1 1 1899644E+07 5 1 1 1 1 1883880E+07 6 1 1 1 1 1868246E+07 7 1 1 1 1 1852742E+07 8 1 1 1 1 1837367E+07 9 1 1 1 1 1822119E+07 10 1 1 1 1 1806998E+07 11 1 1 1 1 1792002E+07 12 1 1 1 1 1777131E+07 13 1 1 1 1 1762383E+07 14 1 1 1 1 1747757E+07 15 1 1 1 1
helliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
5000000E-02 1958 175 162 33 15 4200000E-02 1959 175 163 33 15 3500000E-02
1960 175 164 33 15 3000000E-02 1961 175 165 33 15 2500000E-02 1962 175 166 33 15
2000000E-02 1963 175 167 33 15 1500000E-02 1964 175 168 33 15 1000000E-02
1965 175 169 33 15 6900000E-03 1966 175 170 33 15 5000000E-03 1967 175 171 33 15
3000000E-03 1968 175 172 33 15 1000000E-04 1969 175 172 33 15
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
31
42 ECCO libraries JEFF 31
bullThey are binary files They can be converted into ASCII format (and vice-versa) by specific
ERANOS modules (BITOCICITOBI) but they must be in binary format to be used by the ERANOS modules requiring libraries as input data (egECCO)
bullThe 1968-group library is rather large although it contains only the most important nuclides for the reactor flux calculations The 175 172 and 33 group libraries contain all the isotopes
bullThey depend on a reference file which allows to associate a given nuclide to its data This file also contains nuclide characteristics (mass disintegration constant released energies) common to all data files The same reference file may be used with several libraries under the strict condition that nuclides are in the same order This is the case for the 1968 172 and 33 group libraries which all depend on a unique file while the 175-group library depends on another reference file
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
32
421 THE 1968 172 AND 33 ENERGY GROUPS LIBRARIESThe 1968 group library
bullThe 1968-group library contains fewer nuclides than the other ones only the 112 first nuclides from H1 to ccah2 are present bull103 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds with P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files (H-H2O H-CH2 H-ZrHx D-D2O Be and Mg metal Ca-CaH2 H-CaH2 and C-graphite)
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
33
The 172 group library (XMAS group structure)
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides with P0 to P3 scattering 2936 5736 9736 K data free gas thermal scattering
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
34
The 33 energy groups library
bull103 nuclides condensed from the 1968 energy groups library P0 and P1 scattering 2936 5736 9736 14736 29736 K data free gas thermal scattering and probability table representation of resonance shielding over the entire energy range
+bull9 compounds condensed from the 1968 energy groups library P0 and P1 scattering nuclide dependent multi-temperature cross sections thermal files
+bull277 nuclides condensed from 172 energy groups library P0-P3 scattering 2936 5736 9736 K data free gas thermal scattering
+bull57 PSEUDO fission products 19 global pseudo fission products for Na-cooled FRs (name=fp+fissile nuclide name) 19 solid pseudo fission products for Na-cooled FRs (name=fps+fissile nuclide name) 19 global pseudo fission products for gaz-cooled FRs with large amounts of C containing structure (name=fpg+fissile nuclide name)
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
35
Nuclides presents only in 33 energy groups libraries fpTh232 fpU233 fpU234 fpU235 fpU236 fpU238 fpNp237 fpNp238 fpPu238 fpPu239 fpPu240 fpPu241 fpPu242 fpAm241 fpAm242m fpAm243 fpCm243 fpCm244 fpCm245 sfpTh232 sfpU233 sfpU234 sfpU235 sfpU236 sfpU238 sfpNp237 sfpNp238 sfpPu238 sfpPu239 sfpPu240 sfpPu241 sfpPu242 sfpAm241 sfpAm242m sfpAm243 sfpCm243 sfpCm244 sfpCm245 fpgTh232 fpgU233 fpgU234 fpgU235 fpgU236 fpgU238 fpgNp237 fpgNp238 fpgPu238 fpgPu239 fpgPu240 fpgPu241 fpgPu242 fpgAm241 fpgAm242m fpgAm243 fpgCm243 fpgCm244 fpgCm245
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
36
43 ECCO libraries ENDFB 68
bull All data are coming from ENDFB 68 evaluations except Ar40 Ni59 In115 which could not be processed and were taken from JEFF 31 evaluations
bull 320 Nuclides
bull The 1968 group libraryThe 1968-group library contains fewer nuclides than the other ones only the 95 first nuclides from H1 to poly are present
89 nuclides with P0 and P1 scattering 2936 5736 9736 14736 29736 K datahellip+ 6 compounds with P0 and P1 scatteringhellip
bull The 172 group library (XMAS group structure)89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides with P0 to P3 scattering 2936 5736 9736 Khellip
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
37
bullThe 33 energy groups library89 nuclides condensed from the 1968 energy groups library +6 compounds condensed from 1968 energy groups library +225 nuclides condensed from 172 energy groups libraryhellip
44 ECCO libraries JENDL 33
bullAll data are coming from JENDL 33 evaluations except Au197 and Nb93 which could not be processed and were taken from JEFF 31 evaluations
bull338 Nuclideshelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphelliphellip
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
38
45 Processing scheme
bull Evaluated libraries in ENDF-6 format
bull It mainly relies on two important processing codes
NJOY (resonance integrals fission spectrum averaged Graphical plots of cross sections angular distributions and emitted spectra for
all isotopes and elements at all temperatures)
CALENDF (convert resolved and unresolved resonance parameters from ENDF-6 structured evaluations into temperature dependent
point- wise cross-sections it generates cross-section probability tablesldquo based on Gauss quadrature These represent detailed resonance self shielding within any of the groups and can be
used directly in the ECCO cell code)
and two interface codes MERGE GECCO
all of which have been largely updated since the last ECCOLIB was generatedSome major improvements have been achieved in the format and physical qualities of the basic JEFF-31 evaluations input
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
39
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
40
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
41
The following 40 response functions types and names have been included in the ECCO library tape when present in the original evaluation
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
42
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
43
5 USER LANGUAGE
bullIt is the LU language of the ALOS system Its basic instruction is the calling sentence of a module
bullThe calling sentence is formed as follows The first word is the module name which identifies the function The following terms are specified in the directions for use of the module
bull Generally they are - Created or used SETS - Directives to describe the data to be given by the user - The semicolon ends the sentence
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
44
When the module name expresses without ambiguity the waited resulting SET the LU name of the variable SET preceded by an arrow will immediately follow the module name
CREATION_MACRO -gtma
When the module name expresses without ambiguity the used SET the LU name of the used SET between brackets will immediately follow the module name
EDITION_MACRO (ma)
5 USER LANGUAGE
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
45
MODULE DESCRIPTION STANDARDS
ltlt gtgt means that the data in square brackets are to be given 0 or 1 time
ltlt gtgt0 means that the data in square brackets are to be given 0 or N times
ltlt gtgt1 means that the data in square brackets are to be given 1 or N times
means that the data at the right are exclusive (one and only one)
means that the data at the right are optional that they may exist all
together and that at least one must exist
5 USER LANGUAGE
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
46
6 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation 10487081048708 operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
47
bull Modeled Reactor
Na-cooled (UPu)O2fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegratedaxialblankets(same geometryas fissile)bullLowerupperaxialblanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
48
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
49
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
50
bull MEDIUM_CREATION general
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
51
bull MEDIUM_CREATION simple material
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
52
bull MEDIUM_CREATION mixed material
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
53
bull MEDIUM_CREATION medium
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
54
bull MEDIUM_CREATION homogenous cell
bull MEDIUM_EDITION
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
55
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
56
1 Lattice calculation with ECCO
bull Summary
Basic reactor modeling medium set creation operating conditions ECCO sentence and steps basic set creation for core calculation
Advanced topics heterogeneous cells ECCO routes ECCO step options
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
57
bull Modeled Reactor
Na-cooled (UPu)O2 fast reactor1250 MW (thermal) 500 MW (electric)
Fuel SA geometric data
bull169-pin bundle pin pitch = 0878 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fissile height= 100 cmbullIntegrated axial blankets (same geometryas fissile)bullLowerupper axial blanket height= 2525 cmbullNumberof fuel SAsis the core= 255
Fertile SA geometric databull61-pin bundle pin pitch = 1445 cmbullSpacer wire diameter= 0187 cmbullHexagonal wrapper across-flats = 1165 cm (inner) x 1237 cm (outer)bullSA pitch = 1287 cm Fertile height= 150 cm
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
58
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
59
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
60
bull Module sequence
MEDIUM_CREATION to create materials medium and cellsbullMEDIUM set (output)bullCell description needs mediumbullMedium description needs materials
A medium is a homogeneous collection of materials with volume fractionsA cell is a collection of media with geometrical links with each other
OPERATING_CONDITION to expand medium (optional)MEDIUM set (input and output)
ECCO to perform lattice calculationMEDIUM set (input) Ecco files (output)
BASIC_EDL_CREATION_FROM_ECCO_FILE to create edlMEDIUM set (input and output) Ecco files (input) MICRO and MACRO set (output)
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
61
bull Global Data
---gt EINTEEXT = innerouter volume (Pu+Am)O2(U+Pu+Am)O2 in -gtEINT (250074) -gtEEXT 250
---gt expansion coefficients -gtOXIDE_DIL 100 10528E-05 200 10553E-05 -gtSTEEL_DIL 100 1707E-05 200 1740E-05 -gtSODIUM_DIL 100 865600E-5 200 890300E-5 -gtB4C_DIL 100 04344E-5 200 04468E-5
---gt lists for (initial) trace nuclides -gtHN_TRACESU234 10E-15 U235 10E-15 U236 10E-15 U238 10E-15
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
62
bull MEDIUM_CREATION general
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
63
bull MEDIUM_CREATION simple material
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
64
bull MEDIUM_CREATION mixed material
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
65
bull MEDIUM_CREATION medium
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
66
bull MEDIUM_CREATION homogenous cell
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
67
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
68
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
69
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
70
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
71
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
72
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
73
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
74
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
75
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
76
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
77
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
78
IL SISTEMA DI CALCOLO MODULARE
ERANOS
(EUROPEAN REACTOR ANALYSIS OPTIMIZED SYSTEM)
CORE CALCULATIONS
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
79
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
80
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
81
CORE and GEOMETRY
bull The whole core can be described That covers the disposition of the sub-assemblies the nature and geometry of the blanket the description of the control rods special elementshellip To be complete you shall define the geometry
bull A calculation can be 1D 2D or 3D1D spherical cylindrical or plane2D XY Hexagonal RZ or Rθ3D XYZ or Hexagonal-Z
bull The core creation step is used only for 2D and 3D geometriesIt is optional and all can be described in a geometry creation (warning some ERANOS modules may require a core SET in their input data) When both core and geometry creations are used the core description tells where the subassemblies of different types may be placed and the geometry description where they are actually placed and what are the control rod positions and the boundary conditions
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
82
DIFFUSION and TRANSPORT Solution using the Finite Differences Method
bull The DIFFUSION group solves the diffusion problem with a finite differences method Every geometry mentioned above is available Basically you can calculate the flux but many alternatives are available like adjoint calculations or calculations with an external source
bull The BISTRO (BI-dimensional Sn TRansport Optimiseacute) group solves the transport problem (direct or adjoint) with the SN method For the space variable it also is a finite differences method The available geometries are cylindrical spherical and plane 1D XY and RZ With BISTRO you can also perform perturbation sensitivity and uncertainty calculations but you cannot perform kinetics calculations
VARIANT Nodal Method bull The TGVVARIANT group solves the transport (or diffusion) problem with
a nodal method The available geometries are XY or Hexagonal in 2D and XYZ or Hexagonal-Z in 3D With VARIANT you can also perform kinetics and perturbation calculations
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
83
The Diffusion Modules
bull For any geometry the DIFFUSION group is made with several modules and produces several SETs The breaking-up of the diffusion calculation in functions leads to define several functions with several corresponding modules
bull The specific functions are The geometry definition (hexagonal 2d or 3d or rectangular 1d2d3d) The calculation of the coefficients of the diffusion matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems The definition of the solving method and the calculation of its parameters The definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry The processing of the diffusion iterations The editing of every SET created or used by those functions
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
84
The Diffusion Modules
bull The SETS are GEOMETRY
Hexagonal or rectangular Geometry for calculations
MACRO Macroscopic cross-sections
COEFFICIENTS The coefficients of the matrices made discrete on the calculation geometry
EXTERNAL SOURCE
COEFFICIENTS The external source coefficients made discrete on the calculation geometry
METHOD
The selected solving method and its associated parameters
FLUX The flux vector which is the solution of a diffusion problem
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
85
The Transport Modules
bull The specific functions areThe geometry definition (rectangular 1d or 2d) The calculation of the coefficients of the transport matrices which are the same
for the direct adjoint homogeneous or inhomogeneous problems and which may be executed by the function which calculates the diffusion coefficients
The definition of the solving method and the calculation of its parametersThe definition of the external sources for the inhomogeneous problem The discretisation of those sources on the calculation geometry
The SN method specific functions The definition of the selected weights and cosines The processing of the transport iterations The editing of every SET created or used by those functions
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
86
The Transport Modules
bull Every necessary diffusion function must be used here because the diffusion is used to speed up the transport
bull The SETS areGEOMETRY
Hexagonal or rectangular geometry MACRO
Macroscopic cross-sections COEFFICIENTS
The coefficients of the matrices made discrete on the calculation geometry EXTERNAL SOURCE
METHOD The selected solving method and its associated parameters
COSINES AND WEIGHTS Weights and cosineus of the angular directions
SCALAR FLUX The external source coefficients made discrete on the calculation geometry
The scalar flux vector which is the solution of a transport problem ANGULAR FLUX
The angular flux vector which is the solution of a transport problem
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
87
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
88
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
89
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
90
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
91
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
92
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
93
94
95
96
97
98
99
100
Correction de Maillage Spatial
94
95
96
97
98
99
100
Correction de Maillage Spatial
95
96
97
98
99
100
Correction de Maillage Spatial
96
97
98
99
100
Correction de Maillage Spatial
97
98
99
100
Correction de Maillage Spatial
98
99
100
Correction de Maillage Spatial
99
100
Correction de Maillage Spatial
100
Correction de Maillage Spatial