Post on 18-Jan-2016
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Benchmarks for Data Testing of Iron
China Nuclear Data Center(CNDC) China Nuclear Data Center(CNDC) China Institute of Atomic Energy(CIAE)China Institute of Atomic Energy(CIAE)P.O.Box 275-41,Beijing 102413, P.R.ChinaP.O.Box 275-41,Beijing 102413, P.R.ChinaE-Mail: ping@ciae.ac.cnE-Mail: ping@ciae.ac.cn
Ping Liu
1.Introduction
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CIELO/Iron
According to CIELO project, CNDC are working on the
improvement of Iron evaluations, especially on the
experimental data evaluations of Iron
CNDC validated the evaluations of iron with both
shielding and criticality benchmarks
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The method of benchmarks testing Selecting integral benchmarks Using the transport codes to perform benchmark
simulations Analyzing benchmarking results Providing feedbacks to evaluator Key points of above procedure Suitable benchmarks Quantitative feedbacks to evaluators To meet above requirements, related works have been done at CNDC Study on how to select integral benchmarks Development of nuclear data adjustment code (H. Wu’s
presentation on SG39 meeting, May 2015)
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2.Benchmarks Testing of Iron
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Data processing
Evaluated data library CENDL-3.1 ENDF/B-VII.1 JENDL-4.0 CENDL-NP Processing of evaluated data files NJOY99.396 ACE format library
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Integral benchmarks
Transport Code
MCNP5
Benchmarks Criticality (ICSBEP) Shielding (LLNL, FNS/JAPAN)
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Benchmarks The methodology of selecting benchmarks
- The weight (lost to capture) of 56Fe > 1% Cases of benchmarks
184
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Criticality benchmarking
Criticality benchmarking
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Identification Laboratory Case LabelCladding material
Fuel form Fuel material Reflector materialModerator material
PU-MET-FAST-015 IPPE, Russia Steel Metal / Alloy Plutonium Metal Iron None
PU-MET-FAST-025 VNIIEF, Russia Simplified Model Metal / Alloy Plutonium Metal Steel None
PU-MET-FAST-026 VNIIEF, Russia Simplified Model Metal / Alloy Plutonium Metal Steel None
PU-MET-FAST-028 VNIIEF, Russia Simplified Model Metal / Alloy Plutonium Metal Steel None
PU-MET-FAST-032 VNIIEF, Russia Simplified Model Metal / Alloy Plutonium Metal Steel None
HEU-MET-FAST-013 LANL, USA .0625-in.-thick Fe Polyethylene Metal / Alloy Uranium Metal Polyethylene Polyethylene
HEU-MET-FAST-021 VNIIEF, Russia Simplified Model Metal / Alloy Uranium Metal Steel None
HEU-MET-FAST-024 VNIITF, Russia Metal / Alloy Uranium Metal Steel + Polyethylene None
IEU-MET-FAST-005 VNIIEF, Russia Simplified Model Metal / Alloy Uranium Metal Steel None
IEU-MET-FAST-006 VNIIEF, Russia Simplified Model Metal / Alloy Uranium Metal Duralumin None
HEU-MET-THERM-013 LANL, USA 15-mil-thick Fe Polyethylene Metal /Alloy Uranium Metal Polyethylene Polyethylene
HEU-MET-THERM-015 LANL, USA Polyethylene Metal / Alloy Uranium Metal Polyethylene Polyethylene
HEU-MET-INTER-001 ANL, USA ZPR-9/34 Metal / Alloy Uranium Metal Steel None
PU-MET-INTER-002 ANL, USA ZPR-6/10 Steel Metal /Alloy Plutonium Metal Steel + Iron Graphite
MIX-COMP-FAST-001 ANL, USA ZPR-6/7 Steel Compound Depleted Uranium None
Criticality benchmarking
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Criticality benchmarking
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Criticality benchmarking
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Criticality benchmarking
Identification ALIASEALF (MeV)
Keff ICSBEPuncertainty (1 sigma)
C/E of keff
CENDL-NP CENDL-3.1 ENDF/B-VII.0/1
PU-MET-FAST-015 BR-1-3 1 1.0041 1 0.0026 0.9964 0.9920 1.0014
PU-MET-FAST-025 pmf025 1.27 1 1 0.0022 0.9977 0.9949 0.9987
PU-MET-FAST-026 pmf026 1.16 1 1 0.0026 0.9973 0.9913 0.9988
PU-MET-FAST-028 pmf028 1.12 1 1 0.0024 0.9992 0.9917 0.9994
PU-MET-FAST-032 pmf032 1.25 1 1 0.0022 0.9990 0.9921 0.9986
HEU-MET-FAST-013 VNIITF-CTF-SS-13 0.832 0.999 1 0.0015 0.9996 0.9953 0.9986
HEU-MET-FAST-021 VNIITF-CTF-SS-21 0.796 1 1 0.0026 0.9989 0.9938 0.9975
HEU-MET-FAST-024 VNIITF-CTF-SS-24 0.0811 0.999 1 0.0015 1.0006 1.0028 1.0000
IEU-MET-FAST-005 VNIITF-CTF-SS-5 0.647 1 1 0.0023 1.0015 1.0001 1.0020
IEU-MET-FAST-006 VNIITF-CTF-SS-6 0.639 1 1 0.0025 0.9954 0.9984 0.9961
HEU-MET-THERM-013 hmt013-2 7.51E-08 0.9983 1 0.002 1.0147 1.0210 1.0159
HEU-MET-THERM-015 hmt015 6.52E-08 1.00864 1 0.0021 0.9985 1.0045 1.0001
HEU-MET-INTER-001 ZPR-9/34 0.0294 0.9966 1 0.0026 1.0007 1.0177 1.0044
PU-MET-INTER-002 ZPR-6/10 0.0102 0.9869 1 0.0026 1.0515 1.0404 1.0481
MIX-COMP-FAST-001 ZPR-6/7 0.1050 0.9866 1 0.0023 1.0015 0.9992 1.0005
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Results analysis
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C/E of keff for steel/iron benchmarksC/E of keff for steel/iron benchmarks
(without PMI002 and HMT013_2)
HMT013_2 is not a good one for validating iron data, because the polyethylene brings serious overestimation of keff, but not 56Fe. The similar overestimation of kef
is also occurred in PMI002. Regardless of HMT013 and PMI002, the criticality results of iron are not so bad.
HMT013_2 is not a good one for validating iron data, because the polyethylene brings serious overestimation of keff, but not 56Fe. The similar overestimation of kef
is also occurred in PMI002. Regardless of HMT013 and PMI002, the criticality results of iron are not so bad.
Criticality benchmarking
Criticality benchmarking
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With the increase of weight, keff has an increasing tendencyWith the increase of weight, keff has an increasing tendency
Benchmarks Lawrence Livermore pulsed sphere (LLNL) FNS (JAPAN)
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Shielding benchmarking
Benchmarking results
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Neutron leakage angular flux from 5cm-thick iron
Shielding benchmarking
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Shielding benchmarking
Neutron leakage current from iron sphereNeutron leakage current from iron sphere
The results indicate that cross sections and neutron emission spectra for inelastic scattering reactions are needed to be improvedThe results indicate that cross sections and neutron emission spectra for inelastic scattering reactions are needed to be improved
Shielding benchmarking
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The contribution of secondary neutron in 2-10 MeV is mainly from inelastic scattering of discrete energy level and the continuous energy level
3.Summary
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CENDL-3.1 shows good performance for most criticality benchmarks, but the performance of CENDL-3.1 for shielding benchmarks is not good.
For criticality benchmarking Not all benchmarks are suitable for data testing of Iron HMT013_2 and PMI002 are not suitable to validate the Iron Further study on the selection of benchmarks is needed For shielding benchmarking
The results indicate that cross sections and neutron emission spectra for inelastic scattering reactions data from CENDL are need to be improved.
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