Analysis of VIP-BWR reactor core physics experiments on UO2 and MOX mockup fuel assemblies with CASMO5
Author:
Affiliation:
1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R), Tokyo, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00223131.2019.1626296
Reference17 articles.
1. Analyses of Boiling Water Reactor Mixed-Oxide Critical Experiments with CASMO-4/SIMULATE-3
2. Fiscal 2008 report of improvement and maintenance of nuclear characteristics analysis codes for a full MOX core (Analysis of the VIP-BWR critical experiments). Tokyo (Japan): Nuclear Power Engineering Corporation, Institute of Nuclear Safety; 1997 Mar. (no INS/M-96-06). [in Japanese].
3. Fiscal 2009 report of improvement and maintenance of nuclear characteristics analysis codes for a full MOX core (Study on the VIP-BWR critical experiments). Tokyo (Japan): Nuclear Power Engineering Corporation, Institute of Nuclear Safety; 1998 Mar. (no INS/M-97-27). [in Japanese].
4. Interpretation of the VENUS VIP-BWR program with APOLLO2.8 reference and optimized MOC schemes for 8×8 UO2 and MOX BWR assemblies
Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
1. Monte Carlo calculation analysis of measurements of fission rate distributions in light-water-moderated cores loaded with mixed oxide and UO2 fuels;Journal of Nuclear Science and Technology;2021-07-22
2. Analysis of VIP-BWR reactor core physics experiments on UO2 and MOX mockup fuel assemblies - part 2: analysis with SIMULATE5;Journal of Nuclear Science and Technology;2019-07-18
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