Analysis of VIP-BWR reactor core physics experiments on UO2 and MOX mockup fuel assemblies with CASMO5-Reference-Cited by-同舟云学术

Analysis of VIP-BWR reactor core physics experiments on UO2 and MOX mockup fuel assemblies with CASMO5

Published:2019-06-09 Issue:11 Volume:56 Page:1047-1058
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Yamamoto Toru¹,Iwahashi Daiki¹,Sakai Tomohiro¹

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

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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