This work was funded by the RCUK Energy Programme[Grant number EP/P012450/1]
FISPACT-IIAn advanced inventory simulationplatform for nuclear observablesMark Gilbert, Thomas Stainer, Greg BaileyUnited Kingdom Atomic Energy AuthorityFISPACT-II workshop
June 19-21, 2019, OECD/NEA, Paris
FISPACT-II workshop June 2019 M. Gilbert2/30
Overview
• Introduction to inventory simulations with FISPACT-II
• Running FISPACT-II: Getting Started and basic execution
• Self-shielding case study: tungsten in a fusion device
• Fusion decay-heat benchmark for nuclear data validation
• Running FISPACT-II: Advanced Usage
• FISPACT-II applications: waste assessment of steels
• FISPACT-II applications: material modelling, scoping anddamage metrics
• Pathways and uncertainties
FISPACT-II workshop June 2019 M. Gilbert3/30
Session 1:Introduction to inventory
simulations with FISPACT-II
FISPACT-II workshop June 2019 M. Gilbert4/30
FISPACT-II
Sublet, Eastwood, Morgan, Gilbert, Fleming, and ArterNucl. Data Sheets 139 (2017) 77137http://dx.doi.org/10.1016/j.nds.2017.01.002
FISPACT-II workshop June 2019 M. Gilbert5/30
What are inventory simulations?• Inventory simulations are used to predict how the
chemical composition of a material will be alteredunder (neutron) irradiation
I and/or by the decay of radioactive species
FISPACT-II workshop June 2019 M. Gilbert6/30
Why is this important?
• changes in composition can have a profound influence onhow a material behaves
I change in mechanical properties; embrittlement, loss of strength,etc. (including from gas production)
I change in thermal properties (conductivity, resistivity)I change in magnetic properties (e.g. in coils of fusion tokamaks)I increase in radioactivity
build-up of radioactive waste
• therefore, it is vital to have reliable predictions of thesetime-dependent changes
I so they can be included in engineering design studies of reactorcomponents (shielding requirements, maintenance schedules, etc.)
I used to define operational limits & lifetimes of componentsI used to evaluate expected masses and costs of waste disposalI & feed into multi-scale (integrated) modelling
FISPACT-II workshop June 2019 M. Gilbert7/30
How do we do them?Inventory rate equations
dNi
dt= −Ni(λi + σiφ)︸ ︷︷ ︸
loss
+∑
j 6=i Nj(λji + σjiφ)︸ ︷︷ ︸creation
• coupled differential equationsI one equation for each nuclide i at concentration NiI solved numerically by FISPACT-II (using Livermore ODE solver,
LSODE) and used to update material composition
• σji : energy-dependent reaction cross sections for j → i reactions(e.g. (n,γ), (n,α), (n,2n), etc.) from nuclear libraries collapsedwith (normalised) neutron energy spectra from neutron transport;σi is sum over all i → j reactions
• decay constants λi , λji (from decay library of measurements)
• total fluxes φ from neutron transport (neutronics) simulations
FISPACT-II workshop June 2019 M. Gilbert8/30
What does this look like?• Pure tungsten
Time: 0.00 seconds
0.01
0.1
1
10
100
1000
104
105
106
conc
entr
atio
n (a
ppm
)
ZN
71
72
73
74
75
76
77
78
79
105 106 107 108 109 110 111 112 113
114 115
116 117
Lu176
Lu177
Lu178
Lu179
Lu180
Lu181
Lu182
Lu183
Lu184
Hf177
Hf178
Hf179
Hf180
Hf181
Hf182
Hf183
Hf184
Hf185
Hf186
Hf187
Ta178
Ta179
Ta180
Ta181
Ta182
Ta183
Ta184
Ta185
Ta186
Ta187
Ta188
Ta189
Ta190
W179
W180
✽ W181
W182
✽ W183
✽ W184
✽ W185
W186
✽ W187
W188
W189
W190
W191
Re180
Re181
Re182
Re183
Re184
Re185
Re186
Re187
Re188
Re189
Re190
Re191
Re192
Os181
Os182
Os183
Os184
Os185
Os186
Os187
Os188
Os189
Os190
Os191
Os192
Os193
Ir182
Ir183
Ir184
Ir185
Ir186
Ir187
Ir188
Ir189
Ir190
Ir191
Ir192
Ir193
Ir194
Pt183
Pt184
Pt185
Pt186
Pt187
Pt188
Pt189
Pt190
Pt191
Pt192
Pt193
Pt194
Pt195
Au185
Au186
Au187
Au188
Au189
Au190
Au191
Au192
Au193
Au194
Au195
Au196
1
2
3
0 1 2
3
4H1
H2
H3
He3
He4
He6
Li5
Li6
Li7
10-2
100
102
104
106
W Re Os Ta Ir Hf H He Pt
Con
cent
ratio
n (a
ppm
)
Element
FISPACT-II workshop June 2019 M. Gilbert8/30
What does this look like?• Pure tungsten
FISPACT-II workshop June 2019 M. Gilbert9/30
http://fispact.ukaea.uk
Inventory simulation platform
• multiphysics platformfor predicting the inventorychanges in materials underboth neutron andcharged-particle interactions
I calculates activation,transmutation, burn-up, dpa,gas production, gammaspectra, etc.
• employs the most up-to-dateinternational nuclear datalibraries containing:
I nuclear reaction data(reaction cross sections)
I radioactive decay data(half-lives and decayschemes)
I fission yield data (ratios)
FISPACT-II workshop June 2019 M. Gilbert10/30
Inventory calculations
Nuclear data libraries:reaction cross sections,
half-lives and decay,fission yields
FISPACT-IIdifferental equation
solver
input file& filename list
e.g. fromNeutron-transport
(MCNP)
Neutron/particle-spectrum& fluxes
Irradiation& cooling
times
Materialcomposition
γ-spectrum
damage rates,dpa,
energy absorption
Inventory(nuclide composition)
evolution in time Transmutationimpurities &
gas production
photontransport &dosimetry
Integrated assessment &Material lifetimes:
modelling &experiment
Radiological response:activity, decay heat
dose, hazard,waste
FISPACT-II workshop June 2019 M. Gilbert10/30
Inventory calculations
Nuclear data libraries:reaction cross sections,
half-lives and decay,fission yields
FISPACT-IIdifferental equation
solver
input file& filename list
e.g. fromNeutron-transport
(MCNP)
Neutron/particle-spectrum& fluxes
Irradiation& cooling
times
Materialcomposition
γ-spectrum
damage rates,dpa,
energy absorption
Inventory(nuclide composition)
evolution in time Transmutationimpurities &
gas production
photontransport &dosimetry
Integrated assessment &Material lifetimes:
modelling &experiment
Radiological response:activity, decay heat
dose, hazard,waste
FISPACT-II workshop June 2019 M. Gilbert11/30
Types of radiological output
• Activity measured in becquerels (Bq) – number ofdisintegrations (decays) per second – the primary measure
I can be separated by decay type – α, β, γ – in FISPACT-IIoutput
• decay heat, measured in kilowatts (kw)I can be separated by decay type - α, β, γI how much heat will be generated in a material even when not
exposed to irradiationI critical to determine if cooling is needed to prevent melting
• γ dose rate, measured in sieverts (Sv) per hourI contact or point dose approximationsI J kg−1 deposition rate of radiation energy in biological tissueI there are also ingestion and inhalation hazard versions
• clearance indexI IAEA based measureI a nuclide can be disposed of as if it were non radioactive when
the index is less than 1
FISPACT-II workshop June 2019 M. Gilbert12/30
Inventory rate equations
dNi
dt= − Ni(λi + σiφ)︸ ︷︷ ︸
loss
+∑
j 6=i Nj(λji + σjiφ)︸ ︷︷ ︸creation
• decay constants λi , λji (s−1)• GETDECAY to read-in from pre-prepared ARRAYX file
I or to create ARRAYX
• (neutron) fluxes φ and energy dependent spectrain neutrons cm−2s−1
• GETXS to collapse (fold) FLUXES file with reactiondata to produce COLLAPX file of σi , σji values (orread from it)
• FLUX to specify total flux φ
FISPACT-II workshop June 2019 M. Gilbert12/30
Inventory rate equations
dNi
dt= − Ni(λi + σiφ)︸ ︷︷ ︸
loss
+∑
j 6=i Nj(λji + σjiφ)︸ ︷︷ ︸creation
• decay constants λi , λji (s−1)• GETDECAY to read-in from pre-prepared ARRAYX file
I or to create ARRAYX
• (neutron) fluxes φ and energy dependent spectrain neutrons cm−2s−1
• GETXS to collapse (fold) FLUXES file with reactiondata to produce COLLAPX file of σi , σji values (orread from it)
• FLUX to specify total flux φ
FISPACT-II workshop June 2019 M. Gilbert12/30
Inventory rate equations
dNi
dt= − Ni(λi + σiφ)︸ ︷︷ ︸
loss
+∑
j 6=i Nj(λji + σjiφ)︸ ︷︷ ︸creation
• decay constants λi , λji (s−1)• GETDECAY to read-in from pre-prepared ARRAYX file
I or to create ARRAYX
• (neutron) fluxes φ and energy dependent spectrain neutrons cm−2s−1
• GETXS to collapse (fold) FLUXES file with reactiondata to produce COLLAPX file of σi , σji values (orread from it)
• FLUX to specify total flux φ
FISPACT-II workshop June 2019 M. Gilbert13/30
φ & spectra from neutron transport– Monte Carlo simulations
§https://mcnp.lanl.gov/
• Geometry of a reactor or otherneutron environment is convertedinto a finite-element model of“cells”
• Then a Monte Carlo simulation(usually with MCNP§) generatesand transports neutrons one(history) at-a-time
I using same nuclear reactionphysics data as an inventorysimulation
I decisions (reaction type,recoil direction, etc.) aremade using probabilities
I statistical results arebuilt-up (tallied) in regionsof interest
-600
-400
-200
0
200
400
600
200 400 600 800 1000 1200 1400
Ver
tical
pos
ition
(cm
)
Radial position (cm)
A
BC
D
ITER finite-element model
FISPACT-II workshop June 2019 M. Gilbert13/30
φ & spectra from neutron transport– Monte Carlo simulations
§https://mcnp.lanl.gov/
• Geometry of a reactor or otherneutron environment is convertedinto a finite-element model of“cells”
• Then a Monte Carlo simulation(usually with MCNP§) generatesand transports neutrons one(history) at-a-time
I using same nuclear reactionphysics data as an inventorysimulation
I decisions (reaction type,recoil direction, etc.) aremade using probabilities
I statistical results arebuilt-up (tallied) in regionsof interest Initial trajectories for a neutron beam test set-up
FISPACT-II workshop June 2019 M. Gilbert14/30
Typical result for a fusion design
FISPACT-II workshop June 2019 M. Gilbert15/30
FBR – superphenix Fast Breeder ReactorHFR – High Flux Reactor, Petten
PWR – Pressurized Water-cooled Reactor
Neutron irradiation fields: fusion vs. fission• For a fusion DEMOnstration power plant
& typical fission reactors:
108
109
1010
1011
1012
1013
1014
1015
10-3 10-2 10-1 100 101 102 103 104 105 106 107
Neu
tron
flux
(n
cm-2
s-1
)pe
r le
thar
gy in
terv
al
Neutron Energy (eV)
PWRHFRFBR
DEMO-FW
6 8 10 12 14 16 18 20
Neutron Energy (MeV)
• fusion spectrum in first wall (FW) dominated by 14 MeV peak
• well-moderated (averaged) fission spectra don’t have such dominant peaksbut can have tails that explore the 14 MeV region of fusion
total fluxes φ:(×1014 n cm−2 s−1)
DEMO 6FBR 24HFR 5
PWR 3
FISPACT-II workshop June 2019 M. Gilbert16/30
Inventory calculations
FISPACT-IIdifferental equation
solver
input file& filename list
e.g. fromNeutron-transport
(MCNP)
Neutron/particle-spectrum& fluxes
Irradiation& cooling
times
Materialcomposition
γ-spectrum
damage rates,dpa,
energy absorption
Inventory(nuclide composition)
evolution in time Transmutationimpurities &
gas production
photontransport &dosimetry
Integrated assessment &Material lifetimes:
modelling &experiment
Radiological response:activity, decay heat
dose, hazard,waste
Nuclear data libraries:reaction cross sections,
half-lives and decay,fission yields
FISPACT-II workshop June 2019 M. Gilbert16/30
Inventory calculations
FISPACT-IIdifferental equation
solver
input file& filename list
e.g. fromNeutron-transport
(MCNP)
Neutron/particle-spectrum& fluxes
Irradiation& cooling
times
Materialcomposition
γ-spectrum
damage rates,dpa,
energy absorption
Inventory(nuclide composition)
evolution in time Transmutationimpurities &
gas production
photontransport &dosimetry
Integrated assessment &Material lifetimes:
modelling &experiment
Radiological response:activity, decay heat
dose, hazard,waste
Nuclear data libraries:reaction cross sections,
half-lives and decay,fission yields
FISPACT-II workshop June 2019 M. Gilbert17/30
Nuclear data libraries – recommendation
TENDL (latest version 2017†)
• TALYS-based Evaluated Nuclear Data Libraries
• generated using various physical, theoretical, andsemi-empirical models
• fully-automated production with complete coverage ofnuclide & reaction set
I avoids under-estimation due to missing data
• contains data for 2809 target nuclides with half-lives > 1second
I the FISPACT-II decay files includes data on a further 1000radionuclides with sub-second half-lives
• processed version for FISPACT-II covers energies up to1 GeV
I in a fine, high-resolution 709 energy group structure
†A. J. Koning, D. Rochman, et al.Release date: December 30, 2017.https://tendl.web.psi.ch/tendl_2017/tendl2017.html
FISPACT-II workshop June 2019 M. Gilbert18/30
TENDL nuclide coverage• Target nuclide coverage in TENDL libraries is more
complete than elsewhere:
0
20
40
60
80
100
120
0 20 40 60 80 100 120 140 160 180
N=28
N=50 N=82 N=126
Z=28
Z=50
Z=82
Z (
num
ber
of p
roto
ns)
N (number of neutrons)
TENDL-2015 [2809 (544) target nuclides (isomers)]ENDF/B-VII.1 [423 (10) target nuclides (isomers)]
255 stable nuclides• Many more
isomeric states areincluded as bothtargets (parents)and daughters ofreactions – vitalfor correctprediction ofactivity
FISPACT-II workshop June 2019 M. Gilbert19/30
Why is nuclide coverage important?• Comparison to 5 minute experimental irradiation
of pure palladium
• a complex case with many contributing nuclidesI particularly metastables: 108mRh, 109mPd, and 106mRhI a mixture of (n,2n) and (n,p) reactions dominateI TENDL-2017 outperforms all others
1E-03
1E-02
1E-01
1E+00
0 10 20 30 40 50 60
Hea
t O
utp
ut
[µW
/g]
Time after irradiation [minutes]
FNS-00 5 Min. Irradiation - Pd
FNS ExperimentJEFF-3.3EAF2010
ENDF/B-VIII.0TENDL-2017
1E-03
1E-02
1E-01
1E+00
1E-06 1E-05 1E-04
Min Hour5m 10m
He
at
Ou
tpu
t [µ
W/g
]Time after irradiation [years]
FNS-00 5 Min. Irradiation - Pd - TENDL-2017
totalPd109Rh106mRh108mRh106Rh104Pd109mPd107mExp
TENDL-2017 ENDF/B-VIII.0 JEFF-3.3 EAF2010mean % diff. from E 8 64 32 24
Total decay-heat
Nuclear contributions
FISPACT-II workshop June 2019 M. Gilbert19/30
Why is nuclide coverage important?• Comparison to 5 minute experimental irradiation
of pure palladium
• a complex case with many contributing nuclidesI particularly metastables: 108mRh, 109mPd, and 106mRhI a mixture of (n,2n) and (n,p) reactions dominateI TENDL-2017 outperforms all others
1E-03
1E-02
1E-01
1E+00
0 10 20 30 40 50 60
Hea
t O
utp
ut
[µW
/g]
Time after irradiation [minutes]
FNS-00 5 Min. Irradiation - Pd
FNS ExperimentJEFF-3.3EAF2010
ENDF/B-VIII.0TENDL-2017
0
20
40
60
80
100
1E-06 1E-05 1E-04
Min Hour5m 10m
% d
eca
y h
ea
t co
ntr
ibu
tio
nTime after irradiation [years]
FNS-00 5 Min. Irradiation - Pd - TENDL-2017
Pd109Rh106mRh108mRh106Rh104Pd109mPd107m
TENDL-2017 ENDF/B-VIII.0 JEFF-3.3 EAF2010mean % diff. from E 8 64 32 24
Total decay-heat
% Nuclear contributions
FISPACT-II workshop June 2019 M. Gilbert20/30
Palladium nuclide comparisons
• EAF2010 overpredicts 108mRhproduction
• ENDF/B-VIII.0 & JEFF-3.3(not shown) miss 108mRh,109mPd, and 106mRh
• This example is part of thedecay-heat benchmark used tovalidate FISPACT-II – see laterlecture
1E-03
1E-02
1E-01
1E+00
1E-06 1E-05 1E-04
Min Hour5m 10m
Heat O
utp
ut [µ
W/g
]
Time after irradiation [years]
FNS-00 5 Min. Irradiation - Pd - TENDL-2017
totalPd109Rh106mRh108mRh106Rh104Pd109mPd107m00 Exp
1E-03
1E-02
1E-01
1E+00
1E-06 1E-05 1E-04
Min Hour5m 10m
Heat O
utp
ut [µ
W/g
]
Time after irradiation [years]
FNS-00 5 Min. Irradiation - Pd - EAF2010
totalPd109Rh106mRh108mRh106Rh104Pd109mPd107m00 Exp
1E-03
1E-02
1E-01
1E+00
1E-06 1E-05 1E-04
Min Hour5m 10m
Heat O
utp
ut [µ
W/g
]
Time after irradiation [years]
FNS-00 5 Min. Irradiation - Pd - TENDL-2017
totalPd109Rh106mRh108mRh106Rh104Pd109mPd107mExp
TENDL-2017
EAF2010
FISPACT-II workshop June 2019 M. Gilbert21/30
Inventory rate equations
dNi
dt= − Ni(λi + σiφ)︸ ︷︷ ︸
loss
+∑
j 6=i Nj(λji + σjiφ)︸ ︷︷ ︸creation
• neutron reaction cross sections σin barns (×10−24 cm2)
• GETXS to collapse (fold) data in xs endf ENDFdata folder (or in a crossec file for legacy EAF data)with irradiation spectrum to produce COLLAPX fileof σi , σji values (or read from it)
I these are essentially reaction rates per unit flux of the currentirradiation spectrum
FISPACT-II workshop June 2019 M. Gilbert21/30
Inventory rate equations
dNi
dt= − Ni(λi + σiφ)︸ ︷︷ ︸
loss
+∑
j 6=i Nj(λji + σjiφ)︸ ︷︷ ︸creation
• neutron reaction cross sections σin barns (×10−24 cm2)
• GETXS to collapse (fold) data in xs endf ENDFdata folder (or in a crossec file for legacy EAF data)with irradiation spectrum to produce COLLAPX fileof σi , σji values (or read from it)
I these are essentially reaction rates per unit flux of the currentirradiation spectrum
FISPACT-II workshop June 2019 M. Gilbert22/30
Typical cross sections σ
10-5
10-4
10-3
10-2
10-1
100
101
102
10-2 10-1 100 101 102 103 104 105 106 107
Cro
ss s
ectio
ns (
barn
s)
Neutron Energy (eV)
56Fe (n,γ)56Fe (n,p)56Fe (n,α)56Fe (n,2n)56Fe elastic56Fe total
10-4
10-2
100
102
104
106
10-2 10-1 100 101 102 103 104 105 106 107
Cro
ss s
ectio
ns (
barn
s)
Neutron Energy (eV)
186W (n,γ)186W (n,p)186W (n,α)186W (n,2n)186W elastic186W total
• cross section (xs)≈ ‘reaction likelihood’
• Many different reactionspossible on eachnuclide/isotope
• Some (reaction) channelsare only ‘open’ at highenergy (thresholds)
FISPACT-II workshop June 2019 M. Gilbert23/30
Typical reaction chains (via FISPACT-II tree search algorithm)
• High energy (threshold reactions):
I 56Fe(n,p)56Mn (3 MeV threshold)I 186W(n,2n)185W(β−)185Re (7.2 MeV)
• Low energy (capture and decay chains):I 54Fe(n,γ)55Fe(β+)55Mn(n,γ)56MnI 186W(n,γ)187W(β−)187Re
• Gas production:I helium: 56Fe(n,α)53Cr (negligible xs below 4 MeV)I hydrogen: 63Cu(n,p)63Ni, 63Cu(n,np)62Ni
• Long chains (24-reaction chain)I 153Eu(n,γ)154Eu(n,γ)155Eu(n,γ)156Eu(n,γ)157Eu(β−)
157Gd(n,γ)158Gd(n,γ)159Gd(β−)159Tb(n,γ)160Tb(n,γ)161Tb(β−)161Dy(n,γ)162Dy(n,γ)163Dy(n,γ)164Dy(n,γ)
165Dy(β−)165Ho(n,γ)166Ho(n,γ)167Ho(β−)167Er(n,γ)
168Er(n,γ)169Er(β−)169Tm(n,γ)170Tm(n,γ)171Tm
FISPACT-II workshop June 2019 M. Gilbert24/30
Inventory evolution example
appm - atomic parts per million∗nuclide present in input composition
m – concentration dominated by metastable state
• Evolution in time of compositions from FISPACT-II output
• nuclide picture shown on a ”chart of the nuclides”
• e.g. 5-year irradiation of pure tungsten in DEMO
Time: 0.00 seconds
0.01
0.1
1
10
100
1000
104
105
106
conc
entr
atio
n (a
ppm
)
ZN
71
72
73
74
75
76
77
78
79
105 106 107 108 109 110 111 112 113
114 115
116 117
Lu176
Lu177
Lu178
Lu179
Lu180
Lu181
Lu182
Lu183
Lu184
Hf177
Hf178
Hf179
Hf180
Hf181
Hf182
Hf183
Hf184
Hf185
Hf186
Hf187
Ta178
Ta179
Ta180
Ta181
Ta182
Ta183
Ta184
Ta185
Ta186
Ta187
Ta188
Ta189
Ta190
W179
W180
✽ W181
W182
✽ W183
✽ W184
✽ W185
W186
✽ W187
W188
W189
W190
W191
Re180
Re181
Re182
Re183
Re184
Re185
Re186
Re187
Re188
Re189
Re190
Re191
Re192
Os181
Os182
Os183
Os184
Os185
Os186
Os187
Os188
Os189
Os190
Os191
Os192
Os193
Ir182
Ir183
Ir184
Ir185
Ir186
Ir187
Ir188
Ir189
Ir190
Ir191
Ir192
Ir193
Ir194
Pt183
Pt184
Pt185
Pt186
Pt187
Pt188
Pt189
Pt190
Pt191
Pt192
Pt193
Pt194
Pt195
Au185
Au186
Au187
Au188
Au189
Au190
Au191
Au192
Au193
Au194
Au195
Au196
1
2
3
0 1 2
3
4H1
H2
H3
He3
He4
He6
Li5
Li6
Li7
10-2
100
102
104
106
W Re Os Ta Ir Hf H He Pt
Con
cent
ratio
n (a
ppm
)
ElementZ-2
Z-1
Z
Z+1
N-2 N-1 N N+1
(n,α)
(n,t) (n,d) (n,p)
(n,3n) (n,2n) Originalnucleus
(n,γ)
β+out
(Hf)
(Ta)
(W)
(Re)
α out
β- out
n out
Nucl. Sci. Eng 117 (2014) 291-306
• Large spread of isotopes produced – increasing as a function of time aslonger & longer reaction chains are created
FISPACT-II workshop June 2019 M. Gilbert24/30
Inventory evolution example
appm - atomic parts per million∗nuclide present in input composition
m – concentration dominated by metastable state
• Evolution in time of compositions from FISPACT-II output
• nuclide picture shown on a ”chart of the nuclides”
• e.g. 5-year irradiation of pure tungsten in DEMO
Z-2
Z-1
Z
Z+1
N-2 N-1 N N+1
(n,α)
(n,t) (n,d) (n,p)
(n,3n) (n,2n) Originalnucleus
(n,γ)
β+out
(Hf)
(Ta)
(W)
(Re)
α out
β- out
n out
• Large spread of isotopes produced – increasing as a function of time aslonger & longer reaction chains are created
Nucl. Sci. Eng 117 (2014) 291-306
FISPACT-II workshop June 2019 M. Gilbert25/30
Inventory evolution example
appm - atomic parts per million∗nuclide present in input composition
m – concentration dominated by metastable state
• Evolution in time of compositions from FISPACT-II output
• nuclide picture shown on a ”chart of the nuclides”
• e.g. 5-year irradiation of pure tungsten in DEMO
Time: 0.00 seconds
0.01
0.1
1
10
100
1000
104
105
106
conc
entr
atio
n (a
ppm
)
ZN
71
72
73
74
75
76
77
78
79
105 106 107 108 109 110 111 112 113
114 115
116 117
Lu176
Lu177
Lu178
Lu179
Lu180
Lu181
Lu182
Lu183
Lu184
Hf177
Hf178
Hf179
Hf180
Hf181
Hf182
Hf183
Hf184
Hf185
Hf186
Hf187
Ta178
Ta179
Ta180
Ta181
Ta182
Ta183
Ta184
Ta185
Ta186
Ta187
Ta188
Ta189
Ta190
W179
W180
✽ W181
W182
✽ W183
✽ W184
✽ W185
W186
✽ W187
W188
W189
W190
W191
Re180
Re181
Re182
Re183
Re184
Re185
Re186
Re187
Re188
Re189
Re190
Re191
Re192
Os181
Os182
Os183
Os184
Os185
Os186
Os187
Os188
Os189
Os190
Os191
Os192
Os193
Ir182
Ir183
Ir184
Ir185
Ir186
Ir187
Ir188
Ir189
Ir190
Ir191
Ir192
Ir193
Ir194
Pt183
Pt184
Pt185
Pt186
Pt187
Pt188
Pt189
Pt190
Pt191
Pt192
Pt193
Pt194
Pt195
Au185
Au186
Au187
Au188
Au189
Au190
Au191
Au192
Au193
Au194
Au195
Au196
1
2
3
0 1 2
3
4H1
H2
H3
He3
He4
He6
Li5
Li6
Li7
10-2
100
102
104
106
W Re Os Ta Ir Hf H He Pt
Con
cent
ratio
n (a
ppm
)
Element
• Large spread of isotopes produced – increasing as a function of time aslonger & longer reaction chains are created
Nucl. Sci. Eng 117 (2014) 291-306
FISPACT-II workshop June 2019 M. Gilbert25/30
Inventory evolution example
appm - atomic parts per million∗nuclide present in input composition
m – concentration dominated by metastable state
• Evolution in time of compositions from FISPACT-II output
• nuclide picture shown on a ”chart of the nuclides”
• e.g. 5-year irradiation of pure tungsten in DEMO
• Large spread of isotopes produced – increasing as a function of time aslonger & longer reaction chains are created
Nucl. Sci. Eng 117 (2014) 291-306
FISPACT-II workshop June 2019 M. Gilbert25/30
Inventory evolution example
appm - atomic parts per million∗nuclide present in input composition
m – concentration dominated by metastable state
• Evolution in time of compositions from FISPACT-II output
• nuclide picture shown on a ”chart of the nuclides”
• e.g. 5-year irradiation of pure tungsten in DEMO
Time: 5.00 years
m
m
0.01
0.1
1
10
100
1000
104
105
106
conc
entr
atio
n (a
ppm
)
ZN
71
72
73
74
75
76
77
78
79
105 106 107 108 109 110 111 112 113
114 115
116 117
Lu176
Lu177
Lu178
Lu179
Lu180
Lu181
Lu182
Lu183
Lu184
Hf177
Hf178
Hf179
Hf180
Hf181
Hf182
Hf183
Hf184
Hf185
Hf186
Hf187
Ta178
Ta179
Ta180
Ta181
Ta182
Ta183
Ta184
Ta185
Ta186
Ta187
Ta188
Ta189
Ta190
W179
W180
✽ W181
W182
✽ W183
✽ W184
✽ W185
W186
✽ W187
W188
W189
W190
W191
Re180
Re181
Re182
Re183
Re184
Re185
Re186
Re187
Re188
Re189
Re190
Re191
Re192
Os181
Os182
Os183
Os184
Os185
Os186
Os187
Os188
Os189
Os190
Os191
Os192
Os193
Ir182
Ir183
Ir184
Ir185
Ir186
Ir187
Ir188
Ir189
Ir190
Ir191
Ir192
Ir193
Ir194
Pt183
Pt184
Pt185
Pt186
Pt187
Pt188
Pt189
Pt190
Pt191
Pt192
Pt193
Pt194
Pt195
Au185
Au186
Au187
Au188
Au189
Au190
Au191
Au192
Au193
Au194
Au195
Au196
1
2
3
0 1 2
3
4H1
H2
H3
He3
He4
He6
Li5
Li6
Li7
10-2
100
102
104
106
W Re Os Ta Ir Hf H He Pt
Con
cent
ratio
n (a
ppm
)
Element
• Large spread of isotopes produced – increasing as a function of time aslonger & longer reaction chains are created
Nucl. Sci. Eng 117 (2014) 291-306
FISPACT-II workshop June 2019 M. Gilbert26/30
Radiological response evolution example• e.g. dose rate after 5-year irradiation of pure W in DEMO
• total value for material a standard FISPACT-II output
• nuclide chart shows decay of radionuclides
Time: 5.00 years (irradiation)Total Dose Rate (Sv/hr): 1.32E+05
m m
m m m m m
m m
m m m m
m m
m m
10-6
10-4
10-2
100
102
104
106
Dos
e R
ate
(Sv/
hr)
Z
N
71
72
73
74
75
76
77
78
79
105 106 107 108 109 110 111 112 113
114 115
116 117
Lu176
Lu177
Lu178
Lu179
Lu180
Lu181
Lu182
Lu183
Lu184
Hf177
Hf178
Hf179
Hf180
Hf181
Hf182
Hf183
Hf184
Hf185
Hf186
Hf187
Ta178
Ta179
Ta180
Ta181
Ta182
Ta183
Ta184
Ta185
Ta186
Ta187
Ta188
Ta189
Ta190
W179
W180
W181
W182
W183
W184
W185
W186
W187
W188
W189
W190
W191
Re180
Re181
Re182
Re183
Re184
Re185
Re186
Re187
Re188
Re189
Re190
Re191
Re192
Os181
Os182
Os183
Os184
Os185
Os186
Os187
Os188
Os189
Os190
Os191
Os192
Os193
Ir182
Ir183
Ir184
Ir185
Ir186
Ir187
Ir188
Ir189
Ir190
Ir191
Ir192
Ir193
Ir194
Pt183
Pt184
Pt185
Pt186
Pt187
Pt188
Pt189
Pt190
Pt191
Pt192
Pt193
Pt194
Pt195
Au185
Au186
Au187
Au188
Au189
Au190
Au191
Au192
Au193
Au194
Au195
Au196
1
2
3
0 1 2
3
4H1
H2
H3
He3
He4
He6
Li5
Li6
Li7
10-6
10-4
10-2
100
102
104
106
100 102 104 106 108 1010 1012
1hour
1day
1year
100years
10000years
Dos
e ra
te (
Sv/h
r)
Cooling time (seconds)
m – Dose Rate dominated by metastable nuclide(s)
FISPACT-II workshop June 2019 M. Gilbert26/30
Radiological response evolution example• e.g. dose rate after 5-year irradiation of pure W in DEMO
• total value for material a standard FISPACT-II output
• nuclide chart shows decay of radionuclides
m – Dose Rate dominated by metastable nuclide(s)
FISPACT-II workshop June 2019 M. Gilbert26/30
Radiological response evolution example• e.g. dose rate after 5-year irradiation of pure W in DEMO
• total value for material a standard FISPACT-II output
• nuclide chart shows decay of radionuclides
Time: 1.11E+05 years (cooling)Total Dose Rate (Sv/hr): 5.37E-06
m
10-6
10-4
10-2
100
102
104
106
Dos
e R
ate
(Sv/
hr)
Z
N
71
72
73
74
75
76
77
78
79
105 106 107 108 109 110 111 112 113
114 115
116 117
Lu176
Lu177
Lu178
Lu179
Lu180
Lu181
Lu182
Lu183
Lu184
Hf177
Hf178
Hf179
Hf180
Hf181
Hf182
Hf183
Hf184
Hf185
Hf186
Hf187
Ta178
Ta179
Ta180
Ta181
Ta182
Ta183
Ta184
Ta185
Ta186
Ta187
Ta188
Ta189
Ta190
W179
W180
W181
W182
W183
W184
W185
W186
W187
W188
W189
W190
W191
Re180
Re181
Re182
Re183
Re184
Re185
Re186
Re187
Re188
Re189
Re190
Re191
Re192
Os181
Os182
Os183
Os184
Os185
Os186
Os187
Os188
Os189
Os190
Os191
Os192
Os193
Ir182
Ir183
Ir184
Ir185
Ir186
Ir187
Ir188
Ir189
Ir190
Ir191
Ir192
Ir193
Ir194
Pt183
Pt184
Pt185
Pt186
Pt187
Pt188
Pt189
Pt190
Pt191
Pt192
Pt193
Pt194
Pt195
Au185
Au186
Au187
Au188
Au189
Au190
Au191
Au192
Au193
Au194
Au195
Au196
1
2
3
0 1 2
3
4H1
H2
H3
He3
He4
He6
Li5
Li6
Li7
10-6
10-4
10-2
100
102
104
106
100 102 104 106 108 1010 1012
1hour
1day
1year
100years
10000years
Dos
e ra
te (
Sv/h
r)
Cooling time (seconds)
m – Dose Rate dominated by metastable nuclide(s)
FISPACT-II workshop June 2019 M. Gilbert27/30
Activation response – full nuclide contributions• FISPACT-II automated plotting for (dominant) nuclide contributions as a
function of time
Copper
100
102
104
106
108
1010
1012
1014
10-6 10-4 10-2 100 102 104
DEMO-FWSpecific ActivityMin
HourDay
Spe
cific
Act
ivity
(B
q/kg
)
Decay time (years)
totalFe60Ni59H3Zn65Ni63Co60Co60mCu66Cu62Cu64 short-term
medium-term
long-term
Following 2-year irradiations ina fusion field
• shows which nuclides are important and when
FISPACT-II workshop June 2019 M. Gilbert27/30
Activation response – full nuclide contributions• FISPACT-II automated plotting for (dominant) nuclide contributions as a
function of time
Iron
100
102
104
106
108
1010
1012
1014
10-6 10-4 10-2 100 102 104
DEMO-FWSpecific ActivityMin
HourDay
Spe
cific
Act
ivity
(B
q/kg
)
Decay time (years)
totalH3Mn53Cr51Mn54Mn56Fe55
medium-termshort &
long-term
Following 2-year irradiations ina fusion field
• shows which nuclides are important and when
FISPACT-II workshop June 2019 M. Gilbert27/30
Activation response – full nuclide contributions• FISPACT-II automated plotting for (dominant) nuclide contributions as a
function of time
Aluminium
100
102
104
106
108
1010
1012
1014
10-6 10-4 10-2 100 102 104
DEMO-FWSpecific ActivityMin
HourDay
Spe
cific
Act
ivity
(B
q/kg
)
Decay time (years)
totalAl26H3Al28Mg27Na24 short-term
medium-termlong-term
• note feeding of 28Al(T1/2 = 2.3 min) from
β− decay of 28Mg (notshown, T1/2 = 21 hr)
Following 2-year irradiations ina fusion field
• shows which nuclides are important and when
FISPACT-II workshop June 2019 M. Gilbert27/30
Activation response – full nuclide contributions• FISPACT-II automated plotting for (dominant) nuclide contributions as a
function of time
Tin
100
102
104
106
108
1010
1012
1014
10-6 10-4 10-2 100 102 104
DEMO-FWSpecific ActivityMin
HourDay
Spe
cific
Act
ivity
(B
q/kg
)
Decay time (years)
totalSb126Sb126nSn126Sb126mAg108Ag108mTe125mSn121mSb125Sn111
In111Sn113mSn125mSn113In113mSn123mSn123Sn121Sn119mSn117m
• many nuclides, but canstill see 119mSndominance in themedium-term & 121Sn,121mSn importance atlonger times
Following 2-year irradiations ina fusion field
• but picture can be very complex!!
Time: 0.00 seconds
10-4
10-3
0.01
0.1
1
10
100
1000
104
105
106
conc
entr
atio
n (a
ppm
)
ZN
11
12
13
14
15
16
17
18
19
20
21
22
23
24
25
26
27
28
29
30
31
10 11 12 13 14 15 16 17 18 19
20 21
22
23 24 25
26 27 28
29
30 31
32 33
34 35
36
Na21
Na22
Na23
Na24
Na25
Na26
Na27
Na28
Na29
Na30
Mg22
Mg23
Mg24
Mg25
Mg26
Mg27
Mg28
Mg29
Mg30
Mg31
Al23
Al24
Al25
Al26
Al27
✽ Al28
Al29
Al30
Al31
Al32
Al33
Al34
Si25
Si26
Si27
Si28
✽ Si29
✽ Si30
✽ Si31
Si32
Si33
Si34
Si35
Si36
P28
P29
P30
P31
✽ P32
P33
P34
P35
P36
P37
P38
P39
P40
S29
S30
S31
S32
✽ S33
✽ S34
✽ S35
S36
✽ S37
S38
S39
S40
S41
Cl32
Cl33
Cl34
Cl35
Cl36
Cl37
Cl38
Cl39
Cl40
Cl41
Cl42
Cl43
Cl44
Cl45
Ar33
Ar34
Ar35
Ar36
Ar37
Ar38
Ar39
Ar40
Ar41
Ar42
Ar43
Ar44
Ar45
Ar46
Ar47
K36
K37
K38
K39
K40
K41
K42
K43
K44
K45
K46
K47
K48
Ca37
Ca38
Ca39
Ca40
Ca41
Ca42
Ca43
Ca44
Ca45
Ca46
Ca47
Ca48
Ca49
Sc40
Sc41
Sc42
Sc43
Sc44
Sc45
Sc46
Sc47
Sc48
Sc49
Sc50
Sc51
Sc52
Ti41
Ti42
Ti43
Ti44
Ti45
Ti46
✽ Ti47
✽ Ti48
✽ Ti49
✽ Ti50
✽ Ti51
Ti52
Ti53
Ti54
Ti55
V44
V45
V46
V47
V48
V49
V50
✽ V51
✽ V52
V53
V54
V55
V56
V57
V58
Cr46
Cr47
Cr48
Cr49
Cr50
✽ Cr51
Cr52
✽ Cr53
✽ Cr54
✽ Cr55
Cr56
Cr57
Cr58
Cr59
Mn48
Mn49
Mn50
Mn51
Mn52
Mn53
Mn54
Mn55
✽ Mn56
Mn57
Mn58
Mn59
Mn60
Mn61
Fe49
Fe50
Fe51
Fe52
Fe53
Fe54
✽ Fe55
Fe56
✽ Fe57
✽ Fe58
✽ Fe59
Fe60
Fe61
Fe62
Co52
Co53
Co54
Co55
Co56
Co57
Co58
Co59
✽ Co60
Co61
Co62
Co63
Ni53
Ni54
Ni55
Ni56
Ni57
Ni58
✽ Ni59
Ni60
✽ Ni61
✽ Ni62
✽ Ni63
Ni64
✽
Cu56
Cu57
Cu58
Cu59
Cu60
Cu61
Cu62
Cu63
✽ Cu64
Cu65
✽
Zn58
Zn59
Zn60
Zn61
Zn62
Zn63
Zn64
Zn65
Zn66
Ga63
Ga64
Ga65
Ga66
Ga67
m - concentration dominated by metastable nuclide(s)✽ - nuclide present in initial composition
37
38
39
40
41
42
43
44
45
46
47
48
49
50
51
52
53
48 49 50 51 52 53 54 55 56 57
58
59
60 61 62 63
64 65 66
67
68 69
70 71 72
73 74 75
76
Rb85
Rb86
Rb87
Rb88
Rb89
Rb90
Rb91
Rb92
Rb93
Rb94
Sr86
Sr87
Sr88
Sr89
Sr90
Sr91
Sr92
Sr93
Sr94
Sr95
Sr96
Y87
Y88
Y89
Y90
Y91
Y92
Y93
Y94
Y95
Y96
Y97
Y98
Zr88
Zr89
Zr90
✽ Zr91
✽ Zr92
✽ Zr93
Zr94
✽ Zr95
Zr96
✽ Zr97
Zr98
Zr99
Nb89
Nb90
Nb91
Nb92
Nb93
✽ Nb94
Nb95
Nb96
Nb97
Nb98
Nb99
Nb100
Nb101
Nb102
Nb103
Nb104
Mo90
Mo91
Mo92
✽ Mo93
Mo94
✽ Mo95
✽ Mo96
✽ Mo97
✽ Mo98
✽ Mo99
Mo100
✽ Mo101
Mo102
Mo103
Mo104
Mo105
Tc91
Tc92
Tc93
Tc94
Tc95
Tc96
Tc97
Tc98
Tc99
Tc100
Tc101
Tc102
Tc103
Tc104
Tc105
Tc106
Tc107
Tc108
Tc109
Ru92
Ru93
Ru94
Ru95
Ru96
Ru97
Ru98
Ru99
Ru100
Ru101
Ru102
Ru103
Ru104
Ru105
Ru106
Ru107
Ru108
Ru109
Ru110
Ru111
Rh95
Rh96
Rh97
Rh98
Rh99
Rh100
Rh101
Rh102
Rh103
Rh104
Rh105
Rh106
Rh107
Rh108
Rh109
Rh110
Rh111
Rh112
Rh113
Rh114
Pd96
Pd97
Pd98
Pd99
Pd100
Pd101
Pd102
Pd103
Pd104
Pd105
Pd106
Pd107
Pd108
Pd109
Pd110
Pd111
Pd112
Pd113
Pd114
Pd115
Pd116
Pd117
Pd118
Ag100
Ag101
Ag102
Ag103
Ag104
Ag105
Ag106
Ag107
Ag108
Ag109
Ag110
Ag111
Ag112
Ag113
Ag114
Ag115
Ag116
Ag117
Ag118
Ag119
Ag120
Ag121
Ag122
Cd102
Cd103
Cd104
Cd105
Cd106
Cd107
Cd108
Cd109
Cd110
Cd111
Cd112
Cd113
Cd114
Cd115
Cd116
Cd117
Cd118
Cd119
Cd120
Cd121
Cd122
Cd123
Cd124
In106
In107
In108
In109
In110
In111
In112
In113
In114
In115
In116
In117
In118
In119
In120
In121
In122
In123
In124
In125
Sn107
Sn108
Sn109
Sn110
Sn111
Sn112
✽ Sn113
Sn114
✽ Sn115
✽ Sn116
✽ Sn117
✽ Sn118
✽ Sn119
✽ Sn120
✽ Sn121
Sn122
✽ Sn123
Sn124
✽ Sn125
Sn126
Sb112
Sb113
Sb114
Sb115
Sb116
Sb117
Sb118
Sb119
Sb120
Sb121
Sb122
Sb123
Sb124
Sb125
Sb126
Sb127
Te113
Te114
Te115
Te116
Te117
Te118
Te119
Te120
Te121
Te122
Te123
Te124
Te125
Te126
Te127
Te128
I116
I117
I118
I119
I120
I121
I122
I123
I124
I125
I126
I127
I128
I129
70
71
72
73
74
75
76
77
78
79
105 106 107 108 109 110 111
112 113
114 115
116
Yb175
Yb176
Yb177
Yb178
Yb179
Yb180
Yb181
Lu176
Lu177
Lu178
Lu179
Lu180
Lu181
Lu182
Lu183
Lu184
Hf177
Hf178
Hf179
Hf180
Hf181
Hf182
Hf183
Hf184
Hf185
Hf186
Hf187
Ta178
Ta179
Ta180
✽ Ta181
✽ Ta182
Ta183
Ta184
Ta185
Ta186
Ta187
Ta188
Ta189
W179
W180
✽ W181
W182
✽ W183
✽ W184
✽ W185
W186
✽ W187
W188
W189
W190
Re180
Re181
Re182
Re183
Re184
Re185
Re186
Re187
Re188
Re189
Re190
Re191
Os181
Os182
Os183
Os184
Os185
Os186
Os187
Os188
Os189
Os190
Os191
Os192
Ir182
Ir183
Ir184
Ir185
Ir186
Ir187
Ir188
Ir189
Ir190
Ir191
Ir192
Ir193
Pt183
Pt184
Pt185
Pt186
Pt187
Pt188
Pt189
Pt190
Pt191
Pt192
Pt193
Pt194
Au185
Au186
Au187
Au188
Au189
Au190
Au191
Au192
Au193
Au194
Au195
1
2
3
4
5
6
7
8
0 1 2
3
4
5 6
7 8 9
H1
H2
H3
He3
He4
He6
Li5
Li6
Li7
Li8
Li9
Be6
Be7
Be8
Be9
Be10
Be11
Be12
Be13
B8
B9
B10
✽ B11
✽ B12
B13
B14
C9
C10
C11
C12
✽ C13
✽ C14
C15
N11
N12
N13
N14
✽ N15
✽ N16
O14
O15
O16
✽ O17
✽
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
Con
cent
ratio
n (a
ppm
)
Time (years)
100
102
104
106
0.0 0.5 1.0 1.5 2.0
FeCrWMnVHCTaSiReNTiHeZrAl
OSnCuCoOsMoPSNbNi
Con
cent
ratio
n (a
ppm
)
Time (years)
More complexmaterials:Eurofer steel
More complexmaterials:Eurofer steel
Time: 0.00 secondsTotal Decay Heat (kW/kg): 1.838E-08
Z
N
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
20
21
22
23
24
0 1 2
3
4
5 6
7 8 9
10
11
12 13
14
15
16 17
18 19
20 21
22
23 24 25
26 27 28
29
30 31
32 33
34 35
H1
H2
H3
He3
He4
He6
Li5
Li6
Li7
Li8
Li9
Be6
Be7
Be8
Be9
Be10
Be11
Be12
Be13
B8
B9
B10
B11
B12
B13
B14
B15
C9
C10
C11
C12
C13
C14
C15
C16
C17
N11
N12
N13
N14
N15
N16
N17
N18
N19
N20
O14
O15
O16
O17
O18
O19
O20
O21
O22
F15
F16
F17
F18
F19
F20
F21
F22
F23
F24
Ne17
Ne18
Ne19
Ne20
Ne21
Ne22
Ne23
Ne24
Ne25
Ne26
Ne27
Na20
Na21
Na22
Na23
Na24
Na25
Na26
Na27
Na28
Na29
Na30
Mg21
Mg22
Mg23
Mg24
Mg25
Mg26
Mg27
Mg28
Mg29
Mg30
Mg31
Al23
Al24
Al25
Al26
Al27
Al28
Al29
Al30
Al31
Al32
Al33
Al34
Si25
Si26
Si27
Si28
Si29
Si30
Si31
Si32
Si33
Si34
Si35
Si36
P28
P29
P30
P31
P32
P33
P34
P35
P36
P37
P38
P39
P40
S29
S30
S31
S32
S33
S34
S35
S36
S37
S38
S39
S40
S41
Cl32
Cl33
Cl34
Cl35
Cl36
Cl37
Cl38
Cl39
Cl40
Cl41
Cl42
Cl43
Cl44
Cl45
Ar33
Ar34
Ar35
Ar36
Ar37
Ar38
Ar39
Ar40
Ar41
Ar42
Ar43
Ar44
Ar45
Ar46
Ar47
K36
K37
K38
K39
K40
K41
K42
K43
K44
K45
K46
K47
K48
Ca37
Ca38
Ca39
Ca40
Ca41
Ca42
Ca43
Ca44
Ca45
Ca46
Ca47
Ca48
Ca49
Sc40
Sc41
Sc42
Sc43
Sc44
Sc45
Sc46
Sc47
Sc48
Sc49
Sc50
Sc51
Sc52
Ti41
Ti42
Ti43
Ti44
Ti45
Ti46
Ti47
Ti48
Ti49
Ti50
Ti51
Ti52
Ti53
Ti54
Ti55
V44
V45
V46
V47
V48
V49
V50
V51
V52
V53
V54
V55
V56
V57
V58
Cr46
Cr47
Cr48
Cr49
Cr50
Cr51
Cr52
Cr53
Cr54
Cr55
Cr56
Cr57
Cr58
Cr59
10-910-810-710-610-510-410-310-210-1
Dec
ay H
eat (
kW)
63
64
65
66
67
68
69
70
71
72
73
74
75
76
77
78
79
80
81
82
83
84
85
86
87
88
89
90
91
92
93
94
75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104
105
106
107
108
109
110
111
112 113
114 115 116
117
118 119 120
121 122 123
124 125
126 127
128 129 130
131
132 133
134 135
136
137 138
139 140 141 142
143 144 145
146
147
148
149
150 151 152 153
Eu138
Eu139
Eu140
Eu141
Eu142
Eu143
Eu144
Eu145
Eu146
Eu147
Eu148
Eu149
Eu150
Eu151
Eu152
Eu153
Eu154
Eu155
Eu156
Eu157
Eu158
Eu159
Eu160
Eu161
Eu162
Eu163
Eu164
Eu165
Eu166
Eu167
Gd139
Gd140
Gd141
Gd142
Gd143
Gd144
Gd145
Gd146
Gd147
Gd148
Gd149
Gd150
Gd151
Gd152
Gd153
Gd154
Gd155
Gd156
Gd157
Gd158
Gd159
Gd160
Gd161
Gd162
Gd163
Gd164
Gd165
Gd166
Gd167
Gd168
Gd169
Tb140
Tb141
Tb142
Tb143
Tb144
Tb145
Tb146
Tb147
Tb148
Tb149
Tb150
Tb151
Tb152
Tb153
Tb154
Tb155
Tb156
Tb157
Tb158
Tb159
Tb160
Tb161
Tb162
Tb163
Tb164
Tb165
Tb166
Tb167
Tb168
Tb169
Tb170
Tb171
Dy141
Dy142
Dy143
Dy144
Dy145
Dy146
Dy147
Dy148
Dy149
Dy150
Dy151
Dy152
Dy153
Dy154
Dy155
Dy156
Dy157
Dy158
Dy159
Dy160
Dy161
Dy162
Dy163
Dy164
Dy165
Dy166
Dy167
Dy168
Dy169
Dy170
Dy171
Dy172
Dy173
Ho142
Ho143
Ho144
Ho145
Ho146
Ho147
Ho148
Ho149
Ho150
Ho151
Ho152
Ho153
Ho154
Ho155
Ho156
Ho157
Ho158
Ho159
Ho160
Ho161
Ho162
Ho163
Ho164
Ho165
Ho166
Ho167
Ho168
Ho169
Ho170
Ho171
Ho172
Ho173
Ho174
Ho175
Er143
Er144
Er145
Er146
Er147
Er148
Er149
Er150
Er151
Er152
Er153
Er154
Er155
Er156
Er157
Er158
Er159
Er160
Er161
Er162
Er163
Er164
Er165
Er166
Er167
Er168
Er169
Er170
Er171
Er172
Er173
Er174
Er175
Er176
Er177
Tm145
Tm146
Tm147
Tm148
Tm149
Tm150
Tm151
Tm152
Tm153
Tm154
Tm155
Tm156
Tm157
Tm158
Tm159
Tm160
Tm161
Tm162
Tm163
Tm164
Tm165
Tm166
Tm167
Tm168
Tm169
Tm170
Tm171
Tm172
Tm173
Tm174
Tm175
Tm176
Tm177
Tm178
Tm179
Yb148
Yb149
Yb150
Yb151
Yb152
Yb153
Yb154
Yb155
Yb156
Yb157
Yb158
Yb159
Yb160
Yb161
Yb162
Yb163
Yb164
Yb165
Yb166
Yb167
Yb168
Yb169
Yb170
Yb171
Yb172
Yb173
Yb174
Yb175
Yb176
Yb177
Yb178
Yb179
Yb180
Yb181
Lu150
Lu151
Lu152
Lu153
Lu154
Lu155
Lu156
Lu157
Lu158
Lu159
Lu160
Lu161
Lu162
Lu163
Lu164
Lu165
Lu166
Lu167
Lu168
Lu169
Lu170
Lu171
Lu172
Lu173
Lu174
Lu175
Lu176
Lu177
Lu178
Lu179
Lu180
Lu181
Lu182
Lu183
Lu184
Hf153
Hf154
Hf155
Hf156
Hf157
Hf158
Hf159
Hf160
Hf161
Hf162
Hf163
Hf164
Hf165
Hf166
Hf167
Hf168
Hf169
Hf170
Hf171
Hf172
Hf173
Hf174
Hf175
Hf176
Hf177
Hf178
Hf179
Hf180
Hf181
Hf182
Hf183
Hf184
Hf185
Hf186
Hf187
Hf188
Ta155
Ta156
Ta157
Ta158
Ta159
Ta160
Ta161
Ta162
Ta163
Ta164
Ta165
Ta166
Ta167
Ta168
Ta169
Ta170
Ta171
Ta172
Ta173
Ta174
Ta175
Ta176
Ta177
Ta178
Ta179
Ta180
Ta181
Ta182
Ta183
Ta184
Ta185
Ta186
Ta187
Ta188
Ta189
Ta190
W158
W159
W160
W161
W162
W163
W164
W165
W166
W167
W168
W169
W170
W171
W172
W173
W174
W175
W176
W177
W178
W179
W180
W181
W182
W183
W184
W185
W186
W187
W188
W189
W190
W191
W192
W193
W194
Re160
Re161
Re162
Re163
Re164
Re165
Re166
Re167
Re168
Re169
Re170
Re171
Re172
Re173
Re174
Re175
Re176
Re177
Re178
Re179
Re180
Re181
Re182
Re183
Re184
Re185
Re186
Re187
Re188
Re189
Re190
Re191
Re192
Re193
Re194
Re195
Re196
Re197
Re198
Os162
Os163
Os164
Os165
Os166
Os167
Os168
Os169
Os170
Os171
Os172
Os173
Os174
Os175
Os176
Os177
Os178
Os179
Os180
Os181
Os182
Os183
Os184
Os185
Os186
Os187
Os188
Os189
Os190
Os191
Os192
Os193
Os194
Os195
Os196
Os197
Os198
Os199
Os200
Os201
Ir164
Ir165
Ir166
Ir167
Ir168
Ir169
Ir170
Ir171
Ir172
Ir173
Ir174
Ir175
Ir176
Ir177
Ir178
Ir179
Ir180
Ir181
Ir182
Ir183
Ir184
Ir185
Ir186
Ir187
Ir188
Ir189
Ir190
Ir191
Ir192
Ir193
Ir194
Ir195
Ir196
Ir197
Ir198
Ir199
Ir200
Ir201
Ir202
Pt166
Pt167
Pt168
Pt169
Pt170
Pt171
Pt172
Pt173
Pt174
Pt175
Pt176
Pt177
Pt178
Pt179
Pt180
Pt181
Pt182
Pt183
Pt184
Pt185
Pt186
Pt187
Pt188
Pt189
Pt190
Pt191
Pt192
Pt193
Pt194
Pt195
Pt196
Pt197
Pt198
Pt199
Pt200
Pt201
Pt202
Pt203
Au169
Au170
Au171
Au172
Au173
Au174
Au175
Au176
Au177
Au178
Au179
Au180
Au181
Au182
Au183
Au184
Au185
Au186
Au187
Au188
Au189
Au190
Au191
Au192
Au193
Au194
Au195
Au196
Au197
Au198
Au199
Au200
Au201
Au202
Au203
Au204
Au205
Au206
Hg171
Hg172
Hg173
Hg174
Hg175
Hg176
Hg177
Hg178
Hg179
Hg180
Hg181
Hg182
Hg183
Hg184
Hg185
Hg186
Hg187
Hg188
Hg189
Hg190
Hg191
Hg192
Hg193
Hg194
Hg195
Hg196
Hg197
Hg198
Hg199
Hg200
Hg201
Hg202
Hg203
Hg204
Hg205
Hg206
Hg207
Hg208
Hg209
Hg210
Tl176
Tl177
Tl178
Tl179
Tl180
Tl181
Tl182
Tl183
Tl184
Tl185
Tl186
Tl187
Tl188
Tl189
Tl190
Tl191
Tl192
Tl193
Tl194
Tl195
Tl196
Tl197
Tl198
Tl199
Tl200
Tl201
Tl202
Tl203
Tl204
Tl205
Tl206
Tl207
Tl208
Tl209
Tl210
Tl211
Tl212
Pb178
Pb179
Pb180
Pb181
Pb182
Pb183
Pb184
Pb185
Pb186
Pb187
Pb188
Pb189
Pb190
Pb191
Pb192
Pb193
Pb194
Pb195
Pb196
Pb197
Pb198
Pb199
Pb200
Pb201
Pb202
Pb203
Pb204
Pb205
Pb206
Pb207
Pb208
Pb209
Pb210
Pb211
Pb212
Pb213
Pb214
Pb215
Bi184
Bi185
Bi186
Bi187
Bi188
Bi189
Bi190
Bi191
Bi192
Bi193
Bi194
Bi195
Bi196
Bi197
Bi198
Bi199
Bi200
Bi201
Bi202
Bi203
Bi204
Bi205
Bi206
Bi207
Bi208
Bi209
Bi210
Bi211
Bi212
Bi213
Bi214
Bi215
Bi216
Bi217
Bi218
Po188
Po189
Po190
Po191
Po192
Po193
Po194
Po195
Po196
Po197
Po198
Po199
Po200
Po201
Po202
Po203
Po204
Po205
Po206
Po207
Po208
Po209
Po210
Po211
Po212
Po213
Po214
Po215
Po216
Po217
Po218
Po219
Po220
At193
At194
At195
At196
At197
At198
At199
At200
At201
At202
At203
At204
At205
At206
At207
At208
At209
At210
At211
At212
At213
At214
At215
At216
At217
At218
At219
At220
At221
At222
At223
Rn195
Rn196
Rn197
Rn198
Rn199
Rn200
Rn201
Rn202
Rn203
Rn204
Rn205
Rn206
Rn207
Rn208
Rn209
Rn210
Rn211
Rn212
Rn213
Rn214
Rn215
Rn216
Rn217
Rn218
Rn219
Rn220
Rn221
Rn222
Rn223
Rn224
Rn225
Rn226
Rn227
Rn228
Fr199
Fr200
Fr201
Fr202
Fr203
Fr204
Fr205
Fr206
Fr207
Fr208
Fr209
Fr210
Fr211
Fr212
Fr213
Fr214
Fr215
Fr216
Fr217
Fr218
Fr219
Fr220
Fr221
Fr222
Fr223
Fr224
Fr225
Fr226
Fr227
Fr228
Fr229
Fr230
Fr231
Fr232
Ra202
Ra203
Ra204
Ra205
Ra206
Ra207
Ra208
Ra209
Ra210
Ra211
Ra212
Ra213
Ra214
Ra215
Ra216
Ra217
Ra218
Ra219
Ra220
Ra221
Ra222
Ra223
Ra224
Ra225
Ra226
Ra227
Ra228
Ra229
Ra230
Ra231
Ra232
Ra233
Ra234
Ac206
Ac207
Ac208
Ac209
Ac210
Ac211
Ac212
Ac213
Ac214
Ac215
Ac216
Ac217
Ac218
Ac219
Ac220
Ac221
Ac222
Ac223
Ac224
Ac225
Ac226
Ac227
Ac228
Ac229
Ac230
Ac231
Ac232
Ac233
Ac234
Ac235
Ac236
Th209
Th210
Th211
Th212
Th213
Th214
Th215
Th216
Th217
Th218
Th219
Th220
Th221
Th222
Th223
Th224
Th225
Th226
Th227
Th228
Th229
Th230
Th231
Th232
Th233
Th234
Th235
Th236
Th237
Th238
Pa212
Pa213
Pa214
Pa215
Pa216
Pa217
Pa218
Pa219
Pa220
Pa221
Pa222
Pa223
Pa224
Pa225
Pa226
Pa227
Pa228
Pa229
Pa230
Pa231
Pa232
Pa233
Pa234
Pa235
Pa236
Pa237
Pa238
Pa239
Pa240
U217
U218
U219
U220
U221
U222
U223
U224
U225
U226
U227
U228
U229
U230
U231
U232
U233
U234
U235
U236
U237
U238
U239
U240
U241
U242
U243
U244
U245
Np225
Np226
Np227
Np228
Np229
Np230
Np231
Np232
Np233
Np234
Np235
Np236
Np237
Np238
Np239
Np240
Np241
Np242
Np243
Np244
Np245
Np246
Pu228
Pu229
Pu230
Pu231
Pu232
Pu233
Pu234
Pu235
Pu236
Pu237
Pu238
Pu239
Pu240
Pu241
Pu242
Pu243
Pu244
Pu245
Pu246
Pu247
23
24
25
26
27
28
29
30
31
32
33
34
35
36
37
38
39
40
41
42
43
44
45
46
47
48
49
50
51
52
53
54
55
56
57
58
59
60
61
62
63
64
18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42
43
44
45 46
47 48
49 50
51
52 53
54 55
56 57
58 59
60
61 62
63 64
65
66 67
68 69
70
71 72
73
74 75
76
77
78
79 80 81 82 83
84
85 86
87
88
89 90
91
92 93
94 95 96
97
98
99
100
101
102
V41
V42
V43
V44
V45
V46
V47
V48
V49
V50
V51
V52
V53
V54
V55
V56
V57
V58
V59
V60
V61
V62
V63
V64
V65
Cr42
Cr43
Cr44
Cr45
Cr46
Cr47
Cr48
Cr49
Cr50
Cr51
Cr52
Cr53
Cr54
Cr55
Cr56
Cr57
Cr58
Cr59
Cr60
Cr61
Cr62
Cr63
Cr64
Cr65
Cr66
Cr67
Mn44
Mn45
Mn46
Mn47
Mn48
Mn49
Mn50
Mn51
Mn52
Mn53
Mn54
Mn55
Mn56
Mn57
Mn58
Mn59
Mn60
Mn61
Mn62
Mn63
Mn64
Mn65
Mn66
Mn67
Mn68
Mn69
Fe45
Fe46
Fe47
Fe48
Fe49
Fe50
Fe51
Fe52
Fe53
Fe54
Fe55
Fe56
Fe57
Fe58
Fe59
Fe60
Fe61
Fe62
Fe63
Fe64
Fe65
Fe66
Fe67
Fe68
Fe69
Fe70
Fe71
Fe72
Co47
Co48
Co49
Co50
Co51
Co52
Co53
Co54
Co55
Co56
Co57
Co58
Co59
Co60
Co61
Co62
Co63
Co64
Co65
Co66
Co67
Co68
Co69
Co70
Co71
Co72
Co73
Co74
Co75
Ni48
Ni49
Ni50
Ni51
Ni52
Ni53
Ni54
Ni55
Ni56
Ni57
Ni58
Ni59
Ni60
Ni61
Ni62
Ni63
Ni64
Ni65
Ni66
Ni67
Ni68
Ni69
Ni70
Ni71
Ni72
Ni73
Ni74
Ni75
Ni76
Ni77
Ni78
Cu52
Cu53
Cu54
Cu55
Cu56
Cu57
Cu58
Cu59
Cu60
Cu61
Cu62
Cu63
Cu64
Cu65
Cu66
Cu67
Cu68
Cu69
Cu70
Cu71
Cu72
Cu73
Cu74
Cu75
Cu76
Cu77
Cu78
Cu79
Cu80
Zn54
Zn55
Zn56
Zn57
Zn58
Zn59
Zn60
Zn61
Zn62
Zn63
Zn64
Zn65
Zn66
Zn67
Zn68
Zn69
Zn70
Zn71
Zn72
Zn73
Zn74
Zn75
Zn76
Zn77
Zn78
Zn79
Zn80
Zn81
Zn82
Zn83
Ga56
Ga57
Ga58
Ga59
Ga60
Ga61
Ga62
Ga63
Ga64
Ga65
Ga66
Ga67
Ga68
Ga69
Ga70
Ga71
Ga72
Ga73
Ga74
Ga75
Ga76
Ga77
Ga78
Ga79
Ga80
Ga81
Ga82
Ga83
Ga84
Ga85
Ga86
Ge58
Ge59
Ge60
Ge61
Ge62
Ge63
Ge64
Ge65
Ge66
Ge67
Ge68
Ge69
Ge70
Ge71
Ge72
Ge73
Ge74
Ge75
Ge76
Ge77
Ge78
Ge79
Ge80
Ge81
Ge82
Ge83
Ge84
Ge85
Ge86
Ge87
Ge88
Ge89
As60
As61
As62
As63
As64
As65
As66
As67
As68
As69
As70
As71
As72
As73
As74
As75
As76
As77
As78
As79
As80
As81
As82
As83
As84
As85
As86
As87
As88
As89
As90
As91
As92
Se65
Se66
Se67
Se68
Se69
Se70
Se71
Se72
Se73
Se74
Se75
Se76
Se77
Se78
Se79
Se80
Se81
Se82
Se83
Se84
Se85
Se86
Se87
Se88
Se89
Se90
Se91
Se92
Se93
Se94
Br67
Br68
Br69
Br70
Br71
Br72
Br73
Br74
Br75
Br76
Br77
Br78
Br79
Br80
Br81
Br82
Br83
Br84
Br85
Br86
Br87
Br88
Br89
Br90
Br91
Br92
Br93
Br94
Br95
Br96
Br97
Kr69
Kr70
Kr71
Kr72
Kr73
Kr74
Kr75
Kr76
Kr77
Kr78
Kr79
Kr80
Kr81
Kr82
Kr83
Kr84
Kr85
Kr86
Kr87
Kr88
Kr89
Kr90
Kr91
Kr92
Kr93
Kr94
Kr95
Kr96
Kr97
Kr98
Kr99
Kr100
Rb71
Rb72
Rb73
Rb74
Rb75
Rb76
Rb77
Rb78
Rb79
Rb80
Rb81
Rb82
Rb83
Rb84
Rb85
Rb86
Rb87
Rb88
Rb89
Rb90
Rb91
Rb92
Rb93
Rb94
Rb95
Rb96
Rb97
Rb98
Rb99
Rb100
Rb101
Rb102
Sr73
Sr74
Sr75
Sr76
Sr77
Sr78
Sr79
Sr80
Sr81
Sr82
Sr83
Sr84
Sr85
Sr86
Sr87
Sr88
Sr89
Sr90
Sr91
Sr92
Sr93
Sr94
Sr95
Sr96
Sr97
Sr98
Sr99
Sr100
Sr101
Sr102
Sr103
Sr104
Sr105
Y76
Y77
Y78
Y79
Y80
Y81
Y82
Y83
Y84
Y85
Y86
Y87
Y88
Y89
Y90
Y91
Y92
Y93
Y94
Y95
Y96
Y97
Y98
Y99
Y100
Y101
Y102
Y103
Y104
Y105
Y106
Y107
Y108
Zr78
Zr79
Zr80
Zr81
Zr82
Zr83
Zr84
Zr85
Zr86
Zr87
Zr88
Zr89
Zr90
Zr91
Zr92
Zr93
Zr94
Zr95
Zr96
Zr97
Zr98
Zr99
Zr100
Zr101
Zr102
Zr103
Zr104
Zr105
Zr106
Zr107
Zr108
Zr109
Zr110
Nb81
Nb82
Nb83
Nb84
Nb85
Nb86
Nb87
Nb88
Nb89
Nb90
Nb91
Nb92
Nb93
Nb94
Nb95
Nb96
Nb97
Nb98
Nb99
Nb100
Nb101
Nb102
Nb103
Nb104
Nb105
Nb106
Nb107
Nb108
Nb109
Nb110
Nb111
Nb112
Nb113
Mo83
Mo84
Mo85
Mo86
Mo87
Mo88
Mo89
Mo90
Mo91
Mo92
Mo93
Mo94
Mo95
Mo96
Mo97
Mo98
Mo99
Mo100
Mo101
Mo102
Mo103
Mo104
Mo105
Mo106
Mo107
Mo108
Mo109
Mo110
Mo111
Mo112
Mo113
Mo114
Mo115
Tc85
Tc86
Tc87
Tc88
Tc89
Tc90
Tc91
Tc92
Tc93
Tc94
Tc95
Tc96
Tc97
Tc98
Tc99
Tc100
Tc101
Tc102
Tc103
Tc104
Tc105
Tc106
Tc107
Tc108
Tc109
Tc110
Tc111
Tc112
Tc113
Tc114
Tc115
Tc116
Tc117
Tc118
Ru87
Ru88
Ru89
Ru90
Ru91
Ru92
Ru93
Ru94
Ru95
Ru96
Ru97
Ru98
Ru99
Ru100
Ru101
Ru102
Ru103
Ru104
Ru105
Ru106
Ru107
Ru108
Ru109
Ru110
Ru111
Ru112
Ru113
Ru114
Ru115
Ru116
Ru117
Ru118
Ru119
Ru120
Rh89
Rh90
Rh91
Rh92
Rh93
Rh94
Rh95
Rh96
Rh97
Rh98
Rh99
Rh100
Rh101
Rh102
Rh103
Rh104
Rh105
Rh106
Rh107
Rh108
Rh109
Rh110
Rh111
Rh112
Rh113
Rh114
Rh115
Rh116
Rh117
Rh118
Rh119
Rh120
Rh121
Rh122
Pd91
Pd92
Pd93
Pd94
Pd95
Pd96
Pd97
Pd98
Pd99
Pd100
Pd101
Pd102
Pd103
Pd104
Pd105
Pd106
Pd107
Pd108
Pd109
Pd110
Pd111
Pd112
Pd113
Pd114
Pd115
Pd116
Pd117
Pd118
Pd119
Pd120
Pd121
Pd122
Pd123
Pd124
Ag93
Ag94
Ag95
Ag96
Ag97
Ag98
Ag99
Ag100
Ag101
Ag102
Ag103
Ag104
Ag105
Ag106
Ag107
Ag108
Ag109
Ag110
Ag111
Ag112
Ag113
Ag114
Ag115
Ag116
Ag117
Ag118
Ag119
Ag120
Ag121
Ag122
Ag123
Ag124
Ag125
Ag126
Ag127
Ag128
Ag129
Ag130
Cd95
Cd96
Cd97
Cd98
Cd99
Cd100
Cd101
Cd102
Cd103
Cd104
Cd105
Cd106
Cd107
Cd108
Cd109
Cd110
Cd111
Cd112
Cd113
Cd114
Cd115
Cd116
Cd117
Cd118
Cd119
Cd120
Cd121
Cd122
Cd123
Cd124
Cd125
Cd126
Cd127
Cd128
Cd129
Cd130
Cd131
Cd132
In97
In98
In99
In100
In101
In102
In103
In104
In105
In106
In107
In108
In109
In110
In111
In112
In113
In114
In115
In116
In117
In118
In119
In120
In121
In122
In123
In124
In125
In126
In127
In128
In129
In130
In131
In132
In133
In134
In135
Sn99
Sn100
Sn101
Sn102
Sn103
Sn104
Sn105
Sn106
Sn107
Sn108
Sn109
Sn110
Sn111
Sn112
Sn113
Sn114
Sn115
Sn116
Sn117
Sn118
Sn119
Sn120
Sn121
Sn122
Sn123
Sn124
Sn125
Sn126
Sn127
Sn128
Sn129
Sn130
Sn131
Sn132
Sn133
Sn134
Sn135
Sn136
Sn137
Sb103
Sb104
Sb105
Sb106
Sb107
Sb108
Sb109
Sb110
Sb111
Sb112
Sb113
Sb114
Sb115
Sb116
Sb117
Sb118
Sb119
Sb120
Sb121
Sb122
Sb123
Sb124
Sb125
Sb126
Sb127
Sb128
Sb129
Sb130
Sb131
Sb132
Sb133
Sb134
Sb135
Sb136
Sb137
Sb138
Sb139
Te105
Te106
Te107
Te108
Te109
Te110
Te111
Te112
Te113
Te114
Te115
Te116
Te117
Te118
Te119
Te120
Te121
Te122
Te123
Te124
Te125
Te126
Te127
Te128
Te129
Te130
Te131
Te132
Te133
Te134
Te135
Te136
Te137
Te138
Te139
Te140
Te141
Te142
I108
I109
I110
I111
I112
I113
I114
I115
I116
I117
I118
I119
I120
I121
I122
I123
I124
I125
I126
I127
I128
I129
I130
I131
I132
I133
I134
I135
I136
I137
I138
I139
I140
I141
I142
I143
I144
Xe110
Xe111
Xe112
Xe113
Xe114
Xe115
Xe116
Xe117
Xe118
Xe119
Xe120
Xe121
Xe122
Xe123
Xe124
Xe125
Xe126
Xe127
Xe128
Xe129
Xe130
Xe131
Xe132
Xe133
Xe134
Xe135
Xe136
Xe137
Xe138
Xe139
Xe140
Xe141
Xe142
Xe143
Xe144
Xe145
Xe146
Xe147
Cs112
Cs113
Cs114
Cs115
Cs116
Cs117
Cs118
Cs119
Cs120
Cs121
Cs122
Cs123
Cs124
Cs125
Cs126
Cs127
Cs128
Cs129
Cs130
Cs131
Cs132
Cs133
Cs134
Cs135
Cs136
Cs137
Cs138
Cs139
Cs140
Cs141
Cs142
Cs143
Cs144
Cs145
Cs146
Cs147
Cs148
Cs149
Cs150
Cs151
Ba114
Ba115
Ba116
Ba117
Ba118
Ba119
Ba120
Ba121
Ba122
Ba123
Ba124
Ba125
Ba126
Ba127
Ba128
Ba129
Ba130
Ba131
Ba132
Ba133
Ba134
Ba135
Ba136
Ba137
Ba138
Ba139
Ba140
Ba141
Ba142
Ba143
Ba144
Ba145
Ba146
Ba147
Ba148
Ba149
Ba150
Ba151
Ba152
Ba153
La117
La118
La119
La120
La121
La122
La123
La124
La125
La126
La127
La128
La129
La130
La131
La132
La133
La134
La135
La136
La137
La138
La139
La140
La141
La142
La143
La144
La145
La146
La147
La148
La149
La150
La151
La152
La153
La154
La155
Ce119
Ce120
Ce121
Ce122
Ce123
Ce124
Ce125
Ce126
Ce127
Ce128
Ce129
Ce130
Ce131
Ce132
Ce133
Ce134
Ce135
Ce136
Ce137
Ce138
Ce139
Ce140
Ce141
Ce142
Ce143
Ce144
Ce145
Ce146
Ce147
Ce148
Ce149
Ce150
Ce151
Ce152
Ce153
Ce154
Ce155
Ce156
Ce157
Pr121
Pr122
Pr123
Pr124
Pr125
Pr126
Pr127
Pr128
Pr129
Pr130
Pr131
Pr132
Pr133
Pr134
Pr135
Pr136
Pr137
Pr138
Pr139
Pr140
Pr141
Pr142
Pr143
Pr144
Pr145
Pr146
Pr147
Pr148
Pr149
Pr150
Pr151
Pr152
Pr153
Pr154
Pr155
Pr156
Pr157
Pr158
Pr159
Nd124
Nd125
Nd126
Nd127
Nd128
Nd129
Nd130
Nd131
Nd132
Nd133
Nd134
Nd135
Nd136
Nd137
Nd138
Nd139
Nd140
Nd141
Nd142
Nd143
Nd144
Nd145
Nd146
Nd147
Nd148
Nd149
Nd150
Nd151
Nd152
Nd153
Nd154
Nd155
Nd156
Nd157
Nd158
Nd159
Nd160
Nd161
Pm126
Pm127
Pm128
Pm129
Pm130
Pm131
Pm132
Pm133
Pm134
Pm135
Pm136
Pm137
Pm138
Pm139
Pm140
Pm141
Pm142
Pm143
Pm144
Pm145
Pm146
Pm147
Pm148
Pm149
Pm150
Pm151
Pm152
Pm153
Pm154
Pm155
Pm156
Pm157
Pm158
Pm159
Pm160
Pm161
Pm162
Pm163
Sm128
Sm129
Sm130
Sm131
Sm132
Sm133
Sm134
Sm135
Sm136
Sm137
Sm138
Sm139
Sm140
Sm141
Sm142
Sm143
Sm144
Sm145
Sm146
Sm147
Sm148
Sm149
Sm150
Sm151
Sm152
Sm153
Sm154
Sm155
Sm156
Sm157
Sm158
Sm159
Sm160
Sm161
Sm162
Sm163
Sm164
Eu130
Eu131
Eu132
Eu133
Eu134
Eu135
Eu136
Eu137
Eu138
Eu139
Eu140
Eu141
Eu142
Eu143
Eu144
Eu145
Eu146
Eu147
Eu148
Eu149
Eu150
Eu151
Eu152
Eu153
Eu154
Eu155
Eu156
Eu157
Eu158
Eu159
Eu160
Eu161
Eu162
Eu163
Eu164
Eu165
Gd134
Gd135
Gd136
Gd137
Gd138
Gd139
Gd140
Gd141
Gd142
Gd143
Gd144
Gd145
Gd146
Gd147
Gd148
Gd149
Gd150
Gd151
Gd152
Gd153
Gd154
Gd155
Gd156
Gd157
Gd158
Gd159
Gd160
Gd161
Gd162
Gd163
Gd164
Gd165
Gd166
93
94
95
96
97
98
99
100
137 138 139 140 141 142 143 144 145 146 147 148 149 150 151 152 153
154 155
156 157
158
Np230
Np231
Np232
Np233
Np234
Np235
Np236
Np237
Np238
Np239
Np240
Np241
Np242
Np243
Np244
Np245
Np246
Pu232
Pu233
Pu234
Pu235
Pu236
Pu237
Pu238
Pu239
Pu240
Pu241
Pu242
Pu243
Pu244
Pu245
Pu246
Pu247
Am237
Am238
Am239
Am240
Am241
Am242
Am243
Am244
Am245
Am246
Am247
Am248
Am249
Am250
Cm238
Cm239
Cm240
Cm241
Cm242
Cm243
Cm244
Cm245
Cm246
Cm247
Cm248
Cm249
Cm250
Cm251
Bk243
Bk244
Bk245
Bk246
Bk247
Bk248
Bk249
Bk250
Bk251
Bk252
Bk253
Bk254
Cf244
Cf245
Cf246
Cf247
Cf248
Cf249
Cf250
Cf251
Cf252
Cf253
Cf254
Cf255
Es249
Es250
Es251
Es252
Es253
Es254
Es255
Es256
Es257
Fm250
Fm251
Fm252
Fm253
Fm254
Fm255
Fm256
Fm257
Fm258
Uranium in PWR
Uranium in PWR
FISPACT-II workshop June 2019 M. Gilbert30/30
Summary
• Inventory simulations are a powerful tool for studying theimpact that neutrons (and other irradiating particles) haveon the chemical composition of materials
• FISPACT-II is a world-leading example, with, in particularadvanced features and the ability to utilise the latestnuclear data
• More details about FISPACT-II athttp://fispact.ukaea.uk
• Further reading:I User-manual, validation reports, material response
handbooks, and much more available athttp://fispact.ukaea.uk
I Sublet, Eastwood, Morgan, Gilbert, Fleming, and Arter,”FISPACT-II: An Advanced Simulation System forActivation, Transmutation and Material Modelling”,Nucl. Data Sheets 139 (2017) 77137http://dx.doi.org/10.1016/j.nds.2017.01.002