Journal ArticleDOI
Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project
Marco Pellegrini,Luis E. Herranz,Sonnenkalb M,Terttaliisa Lind,Yu Maruyama,Randall O. Gauntt,Nathan E. Bixler,A. C. Morreale,K. Dolganov,Tuomo Sevón,Didier Jacquemain,Christophe Journeau,JinHo Song,Y. Nishi,Shinya Mizokami +14 more
TLDR
The Organisation for Economic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF), which started in...Abstract:
The Organisation for Economic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF), which started in...read more
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Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings
Egor Kashkarov,Bright Kwame Afornu,Dmitrii V. Sidelev,Maksim Krinitcyn,Veronica Gouws,Andrey M. Lider +5 more
TL;DR: In this paper, the authors introduce the latest results in the development of protective coatings for ATF claddings based on Zr alloys, involving their behavior under normal and accident conditions in light water reactors (LWRs).
Journal ArticleDOI
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3
Luis E. Herranz,Marco Pellegrini,Terttaliisa Lind,Sonnenkalb M,L. Godin-Jacqmin,Claudia López,K. Dolganov,Frédéric Cousin,H. Tamaki,T. W. Kim,H. Hoshi,Nathan Andrews,Tuomo Sevón +12 more
TL;DR: In this article, the authors describe the accident progression in unit 3 of the Fukushima Daiichi nuclear power station as analyzed in the Phase 2 of the OECD/NEA project “Benchmark Study of the Accident at the Daiichi Nuclear Power Plant” (BSAF).
Journal ArticleDOI
40th Anniversary of the first international topical meeting on nuclear reactor thermal-hydraulics: Highlights of thermal-hydraulics research in the past four decades
TL;DR: The NURETH series is the premier topical meeting exclusively dedicated to advances in nuclear reactor thermal-hydraulics (NURETH-1) as mentioned in this paper, which has been held every year since 1989.
Journal ArticleDOI
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project
Akira Nakayoshi,Joy L. Rempe,Marc Barrachin,D. Bottomley,Didier Jacquemain,Christophe Journeau,Viktor Krasnov,Terttaliisa Lind,Richard Lee,Donald Marksberry,Shinya Mizokami,A. C. Morreale,Damian Peko,Marco Pellegrini,JinHo Song +14 more
Journal ArticleDOI
Estimation of the core degradation and relocation at the Fukushima Daiichi Nuclear Power Station Unit 2 based on RELAP/SCDAPSIM analysis
Hiroshi Madokoro,Ikken Sato +1 more
TL;DR: In this paper, the authors used the RELAP/SCDAPSIM code to understand the in-vessel accident progression of 1F Unit 2 (1F2) in order to understand better the mechanism of three pressure peaks measured through late Mar. 14 to early Mar. 15, 2011.
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Detailed source term estimation of the atmospheric release for the Fukushima Daiichi Nuclear Power Station accident by coupling simulations of an atmospheric dispersion model with an improved deposition scheme and oceanic dispersion model
Genki Katata,Genki Katata,Masamichi Chino,Takuya Kobayashi,Hiroaki Terada,Masakazu Ota,Haruyasu Nagai,Mizuo Kajino,Roland R. Draxler,Matthew C. Hort,A. Malo,Tatsuo Torii,Yukihisa Sanada +12 more
TL;DR: In this article, the authors estimate the detailed atmospheric releases during the Fukushima Daiichi nuclear power station (FNPS1) accident using a reverse estimation method which calculates the release rates of radionuclides by comparing measurements of air concentration of a radionside or its dose rate in the environment with the ones calculated by atmospheric and oceanic transport, dispersion and deposition models.
Journal ArticleDOI
Confirmation of severe accident code modeling in light of the findings at Fukushima Daiichi NPPs
TL;DR: In this article, the authors used the investigation results obtained in Fukushima Daiichi NPP for the SA code validation by comparing with investigation results and calculation results, and discussed how to use the analysis results obtained by TEPCO for the validation of SA code.
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