New JENDL-4.0/HE neutron and proton ACE files

被引:1
|
作者
Konno, Chikara [1 ,2 ]
机构
[1] Japan Atom Energy Agcy, Nucl Sci & Engn Ctr, Tokai, Ibaraki, Japan
[2] Japan Atom Energy Agcy, Nucl Sci & Engn Ctr, 2-4 Shirakata, Tokai, Ibaraki 3191195, Japan
关键词
JENDL-4.0/HE; ACE file; heating number; damage energy production cross-section; secondary neutron multiplicity; fission cross-section; LIBRARY;
D O I
10.1080/00223131.2023.2237970
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The JENDL-4.0/HE neutron and proton ACE files were produced in 2017, and those of 22 nuclei for neutron and 25 nuclei for proton were bundled in the PHITS code. Recently, it was found that the following five data in the JENDL-4.0/HE neutron and proton ACE files had any problems: ACE files for N-15 and O-18, heating numbers, damage energy production cross-sections, secondary neutron multiplicities, and fission cross-sections. Thus, new JENDL-4.0/HE neutron and proton ACE files were produced with the problems fixed. This paper describes the problems and how to produce the new neutron and proton ACE files in detail.
引用
收藏
页码:121 / 126
页数:6
相关论文
共 50 条
  • [31] Validation of MVP-II with JENDL-4.0, ENDF/B-VII.1, and JEFF-3.2 through HTC critical experiments
    Shiba, Shigeki
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2019, 56 (07) : 661 - 667
  • [32] Uncertainty analysis for fission product inventories based on covariance data of fission product yields in JENDL-4.0 and ENDF/B-VIII.0
    Fujita, Tatsuya
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2024, 61 (03) : 417 - 427
  • [33] 235U elastic cross-section adjustment in criticality benchmarks - Comparison between JENDL-4.0 and ENDF/-VII.1
    Makhloul, M.
    Boukhal, H.
    El Bardouni, T.
    Kaddour, M.
    Chakir, E.
    El Ouahdani, S.
    ANNALS OF NUCLEAR ENERGY, 2018, 114 : 541 - 550
  • [34] A temperature effect analysis of the KRITZ-1 benchmark based on keff decomposition and using the JENDL-4.0 and ENDF/B-VII.1 libraries
    El Ouahdani, S.
    Boukhal, H.
    Erradi, L.
    Chakir, E.
    Azahra, M.
    El Bardouni, T.
    Makhloul, M.
    Ahmed, A.
    PROGRESS IN NUCLEAR ENERGY, 2018, 109 : 121 - 129
  • [35] Uncertainty analysis of the OECD/NEA LWR UAM benchmark Phase I using CASMO5 with JENDL-4.0 and ENDF/B-VII.1
    Fujita, Tatsuya
    Sakai, Tomohiro
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2020, 57 (07) : 858 - 873
  • [36] Calculations of Nuclear Astrophysics and Californium Fission Neutron Spectrum Averaged Cross Section Uncertainties Using ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0 and Low-fidelity Covariances
    Pritychenko, B.
    NUCLEAR DATA SHEETS, 2015, 123 : 119 - 123
  • [37] Sensitivity and uncertainty analysis on keff due to nuclear data in the KRITZ-2:19-Comparison between JENDL-4.0 and ENDF/B-VII.1
    Ahmed, Abdulaziz
    Boukhal, H.
    El Bardouni, T.
    Makhloul, M.
    Chakir, E.
    El Ouandani, S.
    ANNALS OF NUCLEAR ENERGY, 2019, 129 : 308 - 315
  • [38] Analysis of the SPERT-III E-Core experiment using CASMO5/TRACE/PARCS based on JENDL-4.0 and ENDF/B-VII.1
    Fujita, Tatsuya
    Sakai, Tomohiro
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2019, 56 (06) : 553 - 571
  • [39] Comparison and sensitivity analysis of the core characteristics of a sodium-cooled fast breeder reactor with 750 MWe output evaluated by JENDL-4.0 and ADJ2000R
    Ohgama, Kazuya
    Ohki, Shigeo
    Sugino, Kazuteru
    Okubo, Tsutomu
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2014, 51 (04) : 558 - 567
  • [40] Monte Carlo analysis of KRITZ-2 critical benchmarks on the reactivity temperature coefficient using ENDF/B-VII.1 and JENDL-4.0 nuclear data libraries
    El Ouahdani, S.
    Boukhal, H.
    Erradi, L.
    Chakir, E.
    El Bardouni, T.
    Hajjaji, O.
    Boulaich, Y.
    Benaalilou, K.
    Kaddour, M.
    ANNALS OF NUCLEAR ENERGY, 2016, 87 : 107 - 118