EASY-2005 activation library and
future plans
Robin ForrestEuratom/UKAEA Fusion Association
Culham Science Centre
This work was funded jointly by the United Kingdom Engineering and Physical Sciences Research Council and by EURATOM
OutlineOutlineIntroduction
Need for n-induced data > 20 MeVNeed for d-induced data
SAFEPAQ-IITool for creating activation libraries
EAF-2005The new librariesValidation
New tools for library analysisDeuteron-induced activationWork towards EAF-2005.1 Future work: EAF-2007Conclusions
IntroductionIntroductionUnderstanding and predicting effect of neutrons on materials
is fundamental to fusion technologyEuropean Activation System (EASY) is the European tool Previous versions such as EASY-2003 have an energy
range < 20 MeVMaterials test facilities (IFMIF) use accelerators, high energy
neutron tail upper energy limit is ~55 MeV Need to extend EASY, has been carried out over 2 years,
EASY-2005 is current versionIFMIF will use deuterons, there is a need for a library of
deuteron-induced cross sections that can be used as part of EASY to enable activation studies
European Activation System (EASY)European Activation System (EASY)
EASY
Developer User
SAFEPAQ-II EAF libraries FISPACT User Interface
EAF Cross sections
EAF Decay data
EAF hazards, clearance, transport
SAFEPAQ-IISAFEPAQ-IIMany data sources are used to assemble the EAF libraryAll data stored in relational databasesSAFEPAQ-II is the software tool that enables the databases
to be:ProcessedVisualisedValidatedOutput
Extended to treat above 20 MeVExtended to treat d-induced data
New SAFEPAQ-II featuresNew SAFEPAQ-II features
Able to read IEAF and TALYS libraries New group structures with 211 and 351 energy groupsNew uncertainty group between 20 and 60 MeVMT numbers for summed reactions (MT >200)
e.g. (n,+) = (n,) + (n,n′h) + (n,pt) + (n,n′pd) + (n,2n2p)Validation histograms showing (C/E) for the various reaction
classes produced for any source libraryFor a library now have a choice of incoming particle (n or d)SAFEPAQ-II: User Manual, R.A. Forrest, UKAEA FUS 454,
Issue 6 (January 2005)
Experimental dataExperimental data
The use of experimental data is fundamental to SAFEPAQ-IIInternal database principally at thermal, 30 keV, 14,5 MeVComplete EXFOR (2 CD-ROMs), relevant subset used for
visualisationIntegral data, stored as ‘effective cross sections’ in specified
neutron spectraAnother EXFOR CD-ROM containing d-induced data
produced by NEA Data Bank
The data are used for:Splitting cross sections into ground and isomeric
contributionsRenormalisationValidation
EAF-2005 cross sectionsEAF-2005 cross sectionsEAF-2005 requires data from 20 – 60 MeVCalculated data produced by TALYS for data > 20 MeVSAFEPAQ-II automatically smoothly joins TALYS-5 data at
20 MeV to existing data in EAF-2003 For new reactions (generally with high thresholds) TALYS-5
data are usedA set of new MT numbers agreed with A Koning, allowing up
to 8 particles to be emitted62,637 reactions (12,617 in EAF-2003)50 data sources86 different reaction types (23 in EAF-2003)The European Activation File: EAF-2005 cross section
library, R.A. Forrest, J. Kopecky and J-Ch Sublet, UKAEA FUS 515 (January 2005)
EAF-2005 decay dataEAF-2005 decay data
New reactions will lead to the production of radio-nuclides not considered in the EAF-2003 decay data library
EAF-2005 contains 2,192 nuclides (278 new)The new nuclides also require data on biological hazards,
clearance and A2
The European Activation File: EAF-2005 decay data library, R.A. Forrest, UKAEA FUS 516 (January 2005)
The European Activation File: EAF-2005 biological, clearance and transport libraries, R.A. Forrest, UKAEA FUS 517 (January 2005)
New reaction types (but standard ENDF)New reaction types (but standard ENDF)
(n,2nd) 11 (n,n´3a) 23 (n,2n2a) 30 (n,n'd2a) 35 (n,n´t2a) 36 (n,3np) 42 (n,n´2p) 44 (n,n´pa) 45 (n,3a) 109 (n,t2a) 113 (n,d2a) 114 (n,pd) 115 (n,pt) 116 (n,da) 117
Reaction
MT value
New reaction types (non-standard)New reaction types (non-standard)
(n,5n) 152 (n,6n) 153 (n,2nt) 154 (n,ta) 155 (n,4np) 156 (n,3nd) 157 (n,n´da) 158 (n,2npa) 159 (n,7n) 160 (n,8n) 161 (n,5np) 162 (n,6np) 163Plus 37 further reactions
Reaction
MT value
Data for Data for 2727Al(n,p)Al(n,p)2727MgMg
Smooth join of EAF-2003 with TALYS-5
Al-27(n,p)Mg-27
Final
Cro
ss s
ect
ion (
b)
Energy (eV)
0.0E+00
3.0E-02
6.0E-02
9.0E-02
1.2E-01
1.5E-01
0.0E+00 1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
SystmTSU88ANL87KTO88KTO90AUW00RAS78MUA85TIL92BUC92TIL87TIL92USM85RI 72CHM86BIA78GEL00JAE88BIR76TSU88NPL78KOS82THS85KOS86RI 97JAE93BIA78BIR85BIR85KOS86LAS67BIA83KTY62SHI77HAR60NPL72ANL75ANL75NAP68LAS54ANL75
EAF-2005EAF-2005
Builds on EAF-2004, improves quality of dataFurther extension of SAFEPAQ-IINew differential measurementsNew integral measurementsUse of TALYS-5 dataUse of LEA for improvement of (n,) and (n,p) low energy
dataImprovement of 2 and 4 group uncertainty dataThe charged particle libraries required for SCPR all new –
based on TALYS calculations, also extended to 60 MeV
New differential and integral dataNew differential and integral data
Filatenkov has measured 14 reactions that were discrepantKopecky has searched EXFOR to find all data > 20 MeVA new source of integral data identified:
S. Qaim et al., KfK Jülich in late seventiesNew integral data for Y, Pb, TaUse of FZK and Řež integral data > 20 MeV
TALYS-5 and -5a dataTALYS-5 and -5a data
A calculation for all targets using global parameters output in EAF format by A Koning
Corrects many problems identified in TALYS-4Better physics ‘Smoother’ high energy dataCharged particle emission improved (still not perfect)
Is default choice for > 20 MeV data
TALYS-5 improvement – TALYS-5 improvement – 5858Ni(n,2n)Ni(n,2n)5757NiNiNi-58(n,2n)Ni-57
TALYS-5 TALYS-4
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
2.0E-02
4.0E-02
6.0E-02
8.0E-02
1.0E-01
1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
RI 99KHA96KHA96BUC92KIG84BHU86SST87KTO88AUB82KOS81GEL02ANL87ANL87RAM91KOS82RAB91LNZ92IBJ80GEL02IRK85JAE84IRK82AEP89RI 97IRK85IRK82JAE88
Better fit to data
Less ‘bumps’
New EXFOR data – New EXFOR data – 5656Fe(n,p)Fe(n,p)5656MnMnFe-56(n,p)Mn-56
Final
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
4.0E-02
8.0E-02
1.2E-01
1.6E-01
2.0E-01
0.0E+00 1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
SystmSys20NPT91KTO88SST87OHO91ANL75AEP93KTO90TIL92TIL92RI 78CRC64GEL00AEP98LVN00GEL00BIR76HAM62ANL75RAB91RI 97JAE93MOH82LAS58KOS80TSU84JAE88LAS67LAS58CRC64GEL66ANL75NPT91AEP89AEP89CRC64
EXFOR data > 20 MeV
New EXFOR data - New EXFOR data - 5959Co(n,3n)Co(n,3n)5757CoCoCo-59(n,3n)Co-57
Final TALYS-5 IEAF-2001 MENDL-2
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
2.4E-01
4.8E-01
7.2E-01
9.6E-01
1.2E+00
1.0E+07 1.8E+07 2.7E+07 3.5E+07 4.3E+07 5.2E+07 6.0E+07
JUL80TOH96LAS77TOH99
TALYS-5 in very good agreement with new high energy data
Significant improvement over EAF-2004
Low Energy Approximation (LEA)Low Energy Approximation (LEA)
Represents the region below the effective threshold of (n,p) and (n,) reactions with Q > 0 by resonance data and or pure 1/v (if no resonances exist)
Based on assumption that R = (p)/() or ()/() is constant at low energies
Pd-107
Ag-107 p
R
En (keV)
LEA for LEA for 3939K(n,K(n,))3636ClClK-39(n,a)Cl-36
Final EAF-2003.0
Cro
ss s
ectio
n (b
)
Energy (eV)
1.0E+00
1.0E-08
1.0E-07
1.0E-06
1.0E-05
1.0E-04
1.0E-03
1.0E-02
1.0E-01
6.0E+071.0E-04 1.0E-03 1.0E-02 1.0E-01 1.0E+00 1.0E+01 1.0E+02 1.0E+03 1.0E+04 1.0E+05 1.0E+06 1.0E+07
SystmSys20IFJ65NZW67HAM60HAM58OTC61FRK64HAM62RIC61
EAF-2003
EAF-2005
New differential data – New differential data – 8080Se(n,p)Se(n,p)8080As As Se-80(n,p)As-80
Final EAF-2003.0
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
8.0E-03
1.6E-02
2.4E-02
3.2E-02
4.0E-02
0.0E+00 1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
SystmSys20TUR67KRI04
EAF-2003 based on JEF-2.2
EAF-2005 based on TALYS-5 renormalised to Filatenkov data
Nb-93(n,a)Y-90m
Final EAF-2003.0
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
1.5E-03
3.0E-03
4.5E-03
6.0E-03
7.5E-03
0.0E+00 1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
SystmSys20SEO86 mIRK83KIG85 mAUB82 mORL58 gAUB79 mNPL81 mAEP89 mCIP85 mBUC92 mDEB98 mRI 01 mRI 01 gGEL00 mGEL00 mRAM91 mAEP77 mJAE88 mIBJ75 mLAS61JUL88JUL88 mLRL60GEL87 mGEL87 mGEL88RI 97 mGEL88 m
Integral data – Integral data – 9393Nb(n,Nb(n,))90m90mY Y Nb-93(n,a)Y-90m
Final EAF-2003.0
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
1.5E-03
3.0E-03
4.5E-03
6.0E-03
7.5E-03
0.0E+00 1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
Experimental data
EAF-2003
EAF-2005
Integral C/E improved
EAF-20031.0518, 1.1279EAF-20051.0010, 1.0704
Validation of EASY-2005Validation of EASY-2005
This is part of the current workDetails given in talk by Jura KopeckyWork so far has identified some problems with EAF-2005Validation report will be produced at end of 2005Currently there are 448 reaction studied, of these 208 are
validatedBased on C/E plots of integral data and plots of differential
data as a function of energy
New SAFEPAQ-II toolsNew SAFEPAQ-II tools
Verification and validation of very large EAF-2005 library is difficult – need for additional tools
Systematics show that cross sections at particular energies have a good correlation with parameters such as A or s = (N - Z) / A
Work on maximum cross sections by Manokhin for (n,2n) shows similar trend
SAFEPAQ-II can extract such data from EAF-2005 or one of the data sources (such as TALYS-5) and display a scatter plot against A, Z or s
Line of best fit can be added and reactions discrepant from the trend identified
Cross section analysisCross section analysis
Data source
Reaction
x-axis variable
y-axis variable
Non-threshold reactions need to specify a minimum energy
Option to add a 2nd reaction e.g. (n,2n) + (n,n′p)
Plot
Maximum cross section - (n,2n) for EAF-2005Maximum cross section - (n,2n) for EAF-2005(n,2n) for Final
Even Z,Even N Even,Odd Odd Z,Odd N
Max
cro
ss s
ectio
n (b
)
Atomic Mass (A)
1E-03
1E+01
1E-02
1E-01
1E+00
0 50 100 150 200 250 300
Trend
Hf-178n(n,2n), what is wrong?
Nb-91m(n,2n), what is wrong?
178178Hf(n,2n) and Hf(n,2n) and 178m178mHf(n,2n)Hf(n,2n)Hf-178(n,2n)Hf-177
TALYS-5a
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
5.0E-01
1.0E+00
1.5E+00
2.0E+00
2.5E+00
5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07
Systm
Hf-178(n,2n) data from TALYS-5a, but no data for the high spin Hf-178n isomer in TALYS-5a
Use ADL-3, no renormalisation to systematics and data very small
Need to improve
91m91mNb(n,2n)Nb(n,2n)90g90gNbNbNb-91m(n,2n)Nb-90g
Final
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
6.0E-01
1.2E+00
1.8E+00
2.4E+00
3.0E+00
1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
Systm
Error with first point in TALYS-5, should be 0
Need to improve
Width at half-maximum - (n,2n) for EAF-2005Width at half-maximum - (n,2n) for EAF-2005(n,2n) for Final
Wid
th a
t hal
f-max
XS
(eV
)
Atomic Mass (A)
0E+00
1E+07
2E+07
3E+07
4E+07
5E+07
6E+07
0 50 100 150 200 250 300
Kr-76(n,2n), what is wrong?
7676Kr(n,2n)Kr(n,2n)7575KrKrKr-76(n,2n)Kr-75
Final
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
1.5E-02
3.0E-02
4.5E-02
6.0E-02
7.5E-02
1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
Large width is due to shape of TALYS-5 data, need to improve?
Deuteron-induced dataDeuteron-induced data
IFMIF uses high energy d beams on a flowing lithium targetCorrosion products in the lithium means that reactions of d
with a wide range of elements possibleNeed to be able to calculate the d-induced activationA d library (based on TALYS calculations) is being
constructed, FISPACT will be modified so that the data can be used
The range of targets and reactions is similar to EAF-2005:60,688 reactions2,192 nuclidesBased on calculated data from TALYSVery limited use of experimental data
5858Ni(d,nNi(d,n))5555CoCo
Ni-58(d,na)Co-55
Final
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
1.0E-02
2.0E-02
3.0E-02
4.0E-02
5.0E-02
0.0E+00 1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
PUP63ROC63
Good agreement of EXFOR with TALYS calculation
6363Cu(d,2n)Cu(d,2n)6363ZnZn
Cu-63(d,2n)Zn-63
Final
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
5.0E-02
1.0E-01
1.5E-01
2.0E-01
2.5E-01
5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07
OSA71BLG63
Good agreement of EXFOR with TALYS calculation
5151V(d,2n)V(d,2n)5151CrCr
V-51(d,2n)Cr-51
Final
Cro
ss s
ectio
n (b
)
Energy (eV)
0.0E+00
2.0E-01
4.0E-01
6.0E-01
8.0E-01
1.0E+00
0.0E+00 1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07
CIN93AEP92JUL80 Very poor
agreement of EXFOR with TALYS calculation.
More work needed!
FISPACT-2005FISPACT-2005
Inventory code - calculates arisings of nuclides following neutron exposure
Developed over last 19 years for fusion applicationsFeatures
External libraries of cross section and decay data Elements hydrogen to fermium handled Arbitrary irradiations (multiple pulses) Arbitrary neutron spectrum Gas production and isomers Sensitivity and uncertainty calculations Dominant nuclides and pathways Fissionable actinides Sequential charged particle reactions
Test version has ability to read a d-induced library
EASY-2005.1EASY-2005.1
Obvious errors in the cross sections described above will be corrected
Implement ability to read d-induced library in FISPACTBug fixes in User InterfaceMaintenance release at end of 2005Feedback from validation studies and physics
improvements will be collected and implemented in the next version
Validation report for EASY-2005 distributed at end of 2005
EASY-2007EASY-2007
EAF-2007 implement feedback from integral validationNew TALYS-6 results
Will contain more complete d-induced libraryUse detailed calculations on selected elements (Avrigeanu)Use of EXFOR data or branching and renormalisationUncertainties?
Documentation
Activation handbookActivation handbook
Example of use of EAF-2003 dataAll elements irradiated in fusion relevant neutron spectra544 pages of tabular and graphical data Importance diagrams are spectrum independent Results without running an inventory codeHandbook of Activation Data Calculated Using EASY-2003
M.R. Gilbert and R.A. Forrest, UKAEA report UKAEA FUS 509 (July 2004). (PDF file, size 8.6Mb)
Available for download
ConclusionsConclusions
EAF-2005 completed and distributed to usersValidation and verification during 2005New SAFEPAQ-II tools to help in verificationNeed for maintenance version (EAF-2005.1) to correct
errors and implement d-induced activationValidation and feedback to be used for EAF-2007
All EASY-2005 documentation, Validation reports and the Activation handbook can be downloaded from the web at http://www.fusion.org.uk/easy2005