This work was funded by the RCUK Energy Programme [Grant number EP/P012450/1] FISPACT-II V&V Fusion decay-heat benchmark for nuclear data validation Advanced interrogation capabilities with FISPACT-II Mark Gilbert, United Kingdom Atomic Energy Authority FISPACT-II workshop October 23-25, 2019, Manchester
44
Embed
Fusion decay-heat benchmark for nuclear data validation ... · Fusion decay heat validation, FISPACT-II & TENDL-2017, EAF2010, ENDF/B-VIII.0, JEFF-3.3, and IRDFF-1.05 nuclear data
This document is posted to help you gain knowledge. Please leave a comment to let me know what you think about it! Share it to your friends and learn new things together.
Transcript
This work was funded by the RCUK Energy Programme[Grant number EP/P012450/1]
FISPACT-II V&V
Fusion decay-heat benchmark fornuclear data validationAdvanced interrogation capabilities with FISPACT-II
Mark Gilbert, United Kingdom Atomic Energy AuthorityFISPACT-II workshop
October 23-25, 2019, Manchester
FISPACT-II workshop October 2019 M. Gilbert2/30
Introduction
• Validation & Verification (V&V) is an important part ofthe development and release of FISPACT-II
• A suite of automated validation benchmarks have beencreated to test new releases of both the FISPACT-II codeand the nuclear data libraries
I against international experimental databases
• Results are compiled into open access pdf reports(see fispact.ukaea.uk)
I thousands of pages in total providing a near-completecoverage of the physics landscape for neutron interactions
• Comparison of simulated fission pulse decay heat to carefully interpretedexperimental data
• e.g. 235U thermal (0.0253 eV) pulse comparison
• total andβ-generated decayheat
• simulated withlatest ENDF/B,JEFF, and JENDLlibraries
• Also included inexercise: 233U,238U, 239Pu, 241Pu,232Th, and 237Np
0
0.2
0.4
0.6
0.8
1
1.2
1.4
1.6
0.1 1 10 100 1000 10000 100000
Dec
ay h
eat (
MeV
/fis
sion
)
Time (s)
ENDF/B-VIII.0 nFY+DDJENDL-4.0+JENDL-2015/DDF
JEFF-3.3 nFY+DDGEFY-6.1+ENDF/B-7.1
TobiasDickensLowell
FISPACT-II workshop October 2019 M. Gilbert5/30
Other validation efforts (2)
UKAEA-R(18)005
• Maxwellian-averagedneutron xs comparison
• using KADoNiS astrophysicsexperimental database, whichincludes data for 357 nuclidesat temperatures ranging from 5keV (58 million K) to 100 keV(1.2 billion K)
• e.g. 56Fe results:
• TENDL-2017 xs & comparisonto KADoNiS of average xs atvarious temperatures fordifferent libraries
10-5
10-4
10-3
10-2
10-1
100
101
102
10-1 100 101 102 103 104 105 106 107
Eh=8.50E+05eV
Mic
rosc
opic
cro
ss s
ectio
n (b
)
Nor
mal
ised
rea
ctio
n ra
te
Energy (eV)
TENDL-2017 kT=0 keVkT=5 keV
kT=30 keVkT=80 keV
10-3
10-2
10-1
2 5 3010 100
< A
vera
ge c
ross
sec
tion
(b)
>
Temperature (keV)
TENDL-2017 TENDL-2014
ENDF/B-VIII.0 JENDL-4.0
JEFF-3.3 EAF-2010 KADoNiS
FISPACT-II workshop October 2019 M. Gilbert6/30
Other validations (3)
UKAEA-R(18)004
• Integro-differential V&V
• Comparison of cross section data against integral and differentialdata in the EXFOR database
• more than 400 reactions currently assessed this way (more could be added)
• e.g. 115In(n,γ)differential datacompared toTENDL-2017
• obvious complexityassociated withthree metastablestates of 116In andpotential formis-attribution
Fusion decay heat benchmark• Experiments performed at the Fusion Neutron Source
(FNS) at JAEA in 1996-2000
• aimed at providing fusion-relevant decay-power data forimportant structural materials
• accurate experimental measurements with detailed recordsare ideal for simulation benchmarking
Experiment reports & papers: F. Maekawa M. Wada, Y. Ikeda et al.Tech. Rep. JAERI-Data/Code 98-024, JAERI-Data/Code 98-021,& JAERI 99-055. http://www.jaea.go.jp/jaeri/
• Detailed experimental information (irradiation times,measurement times, material compositions, etc.) have beentranslated into a set of FISPACT-II input files
I these can be rapidly repeated for different nuclear data libraries
• Latest version of exercise compares results from TENDL-2017,ENDF/B-VIII.0, JEFF-3.3, and EAF2010 neutron cross sectionlibraries
I in some cases it is also possible to produce a meaningfulcomparison with the IRDFF-1.05 dosimetry file
• where available, the decay data file associated with each xs libraryis used (i.e. for JEFF and ENDF/B)
• otherwise the “dec 2012” decay database distributed withFISPACT-II is used – applies to TENDL-2017
I 3875 nuclidesI a combination of data from JEFF-3.1.1, JEF-2.2 to produce the
EAF2010 decay file, UK evaluations in UKPADD6.1-6.9, andsupplemented from ENDF/B-VII
FISPACT-II workshop October 2019 M. Gilbert12/30
Typical results and presentation• 5 minute irradiation of pure iron
• decay heat curves fromsimulations with differentlibraries vs. experiment
A case where TENDL-2017 is best• 5 minute 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
TENDL-2017 ENDF/B-VIII.0 JEFF-3.3 EAF2010mean % diff. from E 8 64 32 24
FISPACT-II workshop October 2019 M. Gilbert17/30
A case where TENDL-2017 is best• 5 minute 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
n
Time 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
FISPACT-II workshop October 2019 M. Gilbert18/30
Palladium nuclide comparisons
• EAF2010 overpredicts 108mRhproduction
• ENDF/B-VIII.0 & JEFF-3.3(not shown) miss 108mRh,109mPd, and 106mRh
A case where JEFF-3.3 is best• 7 hour irradiation of sodium
• only JEFF-3.3 matches closely the experimental measurementsI other libraries either under or over predict the production of 22NaI this could be a coincidence due to an experimental artefact –
especially since the IRDFF dosimetry file underpredicts
1E-04
1E-03
1E-02
0 50 100 150 200 250 300 350 400 450
Hea
t O
utp
ut
[µW
/g]
Time after irradiation [days]
FNS-96 7 hours Irradiation - Na2CO3
FNS ExperimentJEFF-3.3EAF2010
ENDF/B-VIII.0TENDL-2017
IRDFF-1.05
1E-05
1E-04
1E-03
1E-02
1E-03 1E-02 1E-01 1E+00
WeekDay
He
at
Ou
tpu
t [µ
W/g
]
Time after irradiation [years]
FNS-96 7 hours Irradiation - Na2CO
3 - JEFF-3.3
totalNa22Na24Exp
1E-05
1E-04
1E-03
1E-02
1E-03 1E-02 1E-01 1E+00
WeekDay
He
at
Ou
tpu
t [µ
W/g
]
Time after irradiation [years]
FNS-96 7 hours Irradiation - Na2CO
3 - JEFF-3.3
totalNa22Na24Exp
JEFF-3.3 results
TENDL-2017 ENDF/B-VIII.0 JEFF-3.3 EAF2010 IRDFF-1.05mean % diff. from E 16 18 4 24 15
FISPACT-II workshop October 2019 M. Gilbert20/30
Sodium nuclide comparisons
1E-05
1E-04
1E-03
1E-02
1E-03 1E-02 1E-01 1E+00
WeekDay
He
at
Ou
tpu
t [µ
W/g
]
Time after irradiation [years]
FNS-96 7 hours Irradiation - Na2CO
3 - TENDL-2017
totalNa22Na24Exp
1E-05
1E-04
1E-03
1E-02
1E-03 1E-02 1E-01 1E+00
WeekDay
He
at
Ou
tpu
t [µ
W/g
]
Time after irradiation [years]
FNS-96 7 hours Irradiation - Na2CO
3 - ENDF/B-VIII.0
totalNa22Na24Exp
1E-05
1E-04
1E-03
1E-02
1E-03 1E-02 1E-01 1E+00
WeekDay
He
at
Ou
tpu
t [µ
W/g
]
Time after irradiation [years]
FNS-96 7 hours Irradiation - Na2CO
3 - EAF2010
totalNa22Na24Exp
1E-05
1E-04
1E-03
1E-02
1E-03 1E-02 1E-01 1E+00
WeekDay
He
at
Ou
tpu
t [µ
W/g
]
Time after irradiation [years]
FNS-96 7 hours Irradiation - Na2CO
3 - JEFF-3.3
totalNa22Na24Exp
1E-05
1E-04
1E-03
1E-02
1E-03 1E-02 1E-01 1E+00
WeekDay
He
at
Ou
tpu
t [µ
W/g
]
Time after irradiation [years]
FNS-96 7 hours Irradiation - Na2CO
3 - TENDL-2017
totalNa22Na24Exp
TENDL-2017 ENDF/B-VIII.0
EAF2010 JEFF-3.3
• 23Na(n,γ)24Na
• 23Na(n,2n)22Na
FISPACT-II workshop October 2019 M. Gilbert21/30
A case where all are wrong (1)• 5 minute irradiation of pure Indium
• no library is close to the experiment
• the TENDL-2017 nuclide profiles suggestan overestimate of 116mIn production
I 116mIn decay profile matches the experimental measurementsbeyond 5 minutes of cooling
I incorrect distribution of 115In(n,γ) to 116In, 116mIn, 116nIn?(T1/2=14.2s, 54.6m, and 2.2s, respectively)
• TENDL-2017 performs better than other modern libraries& slightly better than EAF2010
FISPACT-II workshop October 2019 M. Gilbert28/30
Summary
• The FNS experimental results from Japan offer a uniquevalidation benchmark for inventory simulations infusion-relevant conditions
I they test the cross section data for a significant fraction ofstable nuclides
• Automation of benchmarking against these experimentswith FISPACT-II allows rapid testing of libraries
I quickly provides a global impression of data qualityI but each individual experiment and associated simulations
can have unexpected subtletiesI overall libraries perform well, particularly at low ZI no library succeeds for every caseI new libraries still have something to learn
from older ones ...
FISPACT-II workshop October 2019 M. Gilbert29/30
A case where the “legacy” is best• 5 minute irradiation of pure Iridium
• Only EAF2010 correctly matchesthe experimental profile (and scale)
I the observed decay heat originates from 192mIr in the first 5 minutesof cooling
• instructs FISPACT-II to output <<n>> blocks of data in .grn file1=activity;2=decay-heat;3=dose...
• for each radiological quantity (block) as a function of time:I total with uncertainty (if <<uncert>> equals 1)I contribution to quantity from any nuclide that contributes
<<floor>> % or more at any time
FISPACT-II workshop October 2019 M. Gilbert1/9
Additional Examples
FISPACT-II workshop October 2019 M. Gilbert2/9
A good agreement case
CCFE-R(18)002
• 5 minute irradiation of pure copper
• a straightforward caseentirely dominated by 62Cu
I 63Cu(n,2n)62CuI all library predictions are within a few % of the experiment at all
decay times
1E-02
1E-01
1E+00
1E+01
0 10 20 30 40 50 60
Hea
t O
utp
ut
[µW
/g]
Time after irradiation [minutes]
FNS-00 5 Min. Irradiation - Cu
FNS ExperimentJEFF-3.3EAF2010
ENDF/B-VIII.0TENDL-2017
IRDFF-1.05
1E-03
1E-02
1E-01
1E+00
1E+01
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 - Cu - TENDL-2017
totalNi65Co62mCu64Co62Cu6200 Exp
TENDL-2017 ENDF/B-VIII.0 JEFF-3.3 EAF2010 IRDFF-1.05mean % diff. from E 4 3 5 6 3
FISPACT-II workshop October 2019 M. Gilbert3/9
Copper at longer times
CCFE-R(18)002
• 7 hour irradiation of pure copper
• two-nuclide contribution profile(different nuclides to 5 minute case)and good agreement with all libraries
I 63Cu(n,α)60Co (including isomeric transition via 60mCo)I 65Cu(n,2n)64Cu
1E-05
1E-04
1E-03
1E-02
1E-01
1E+00
0 50 100 150 200 250 300 350 400 450
Hea
t O
utp
ut
[µW
/g]
Time after irradiation [days]
FNS-96 7 hours Irradiation - Cu
FNS ExperimentJEFF-3.3EAF2010
ENDF/B-VIII.0TENDL-2017
IRDFF-1.05
1E-06
1E-05
1E-04
1E-03
1E-02
1E-01
1E+00
1E-03 1E-02 1E-01 1E+00
WeekDay
He
at
Ou
tpu
t [µ
W/g
]Time after irradiation [years]
FNS-96 7 hours Irradiation - Cu - TENDL-2017
totalCo60Cu64Exp
TENDL-2017 ENDF/B-VIII.0 JEFF-3.3 EAF2010 IRDFF-1.05mean % diff. from E 9 9 9 5 12
FISPACT-II workshop October 2019 M. Gilbert4/9
A problem for JEFF-3.3?
CCFE-R(18)002
• 5 minute irradiation of pure zirconium
• JEFF-3.3 underpredicts duringthe first 30 minutes of cooling
I other libraries produce agood match to theexperiment(IRDFF-1.05 only capturesthe low-level production of89Zr via 90Zr(n,2n))
1E-03
1E-02
1E-01
1E+00
1E+01
0 10 20 30 40 50 60
Hea
t O
utp
ut
[µW
/g]
Time after irradiation [minutes]
FNS-00 5 Min. Irradiation - Zr
FNS ExperimentJEFF-3.3EAF2010
ENDF/B-VIII.0TENDL-2017
IRDFF-1.05
1E-04
1E-03
1E-02
1E-01
1E+00
1E+01
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 - Zr - TENDL-2017
totalSr87mY90Y91mZr89Y92Y90mY94Y89mZr89m00 Exp
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
n
Time after irradiation [years]
FNS-00 5 Min. Irradiation - Zr - TENDL-2017
Sr87mY90Y91mZr89Y92Y90mY94Y89mZr89m
TENDL-2017 results
1E-04
1E-03
1E-02
1E-01
1E+00
1E+01
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 - Zr - TENDL-2017
totalSr87mY90Y91mZr89Y92Y90mY94Y89mZr89m00 Exp
FISPACT-II workshop October 2019 M. Gilbert5/9
Zr nuclide contributions
CCFE-R(18)002
• JEFF-3.3 does not include the 90Zr(n,2n)89mZr channelI this is unexpected because it was included in JEFF-3.2