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This work was funded by the RCUK Energy Programme [Grant number EP/P012450/1] FISPACT-II An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom Atomic Energy Authority FISPACT-II workshop June 19-21, 2019, OECD/NEA, Paris
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Page 1: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

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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

Page 3: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

FISPACT-II workshop June 2019 M. Gilbert3/30

Session 1:Introduction to inventory

simulations with FISPACT-II

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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

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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

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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

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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

Page 8: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 9: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

FISPACT-II workshop June 2019 M. Gilbert8/30

What does this look like?• Pure tungsten

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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)

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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

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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

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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

Page 14: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 15: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 16: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 17: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 18: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 19: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

FISPACT-II workshop June 2019 M. Gilbert14/30

Typical result for a fusion design

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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

Page 21: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 22: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 23: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

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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

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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

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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

Page 27: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

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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

Page 29: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

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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)

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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

Page 32: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 33: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 34: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 35: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 36: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 37: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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)

Page 38: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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)

Page 39: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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)

Page 40: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 41: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 42: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 43: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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!!

Page 44: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 45: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

More complexmaterials:Eurofer steel

Page 46: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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

Page 47: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

Uranium in PWR

Page 48: An advanced inventory simulation platform for nuclear ... · An advanced inventory simulation platform for nuclear observables Mark Gilbert, Thomas Stainer, Greg Bailey United Kingdom

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


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