Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase II—Results of Severe Accident Analyses for Unit 1

Luis Enrique Herranz, Marco Pellegrini, Terttaliisa Lind, Martin Sonnenkalb, L. Godin-Jacqmin, Claudia López, K. Dolganov, F. Cousin, H. Tamaki, T. W. Kim, H. Hoshi, Nathan Andrews, Tuomo Sevon

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

2 Citations (Scopus)

Abstract

Phase II of the OECD/NEA Project “Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF)” was established in mid-2015. The objectives have been similar to phase 1 of the project but with an extended analysis period of 3 weeks from the occurrence of the earthquake, a major focus on fission product (FP) behaviour and releases to the environment and the comparison to various data including radiological data and results of backwards calculations of the source term. Nine organizations of six countries (CIEMAT;, IAE, JAEA and NRA Japan; CEA, IRSN France; IBRAE Russia, KAERI Korea; NRC/DOE/SNL U.S.A.; VTT Finland) submitted results of their calculated severe accident scenarios for Unit 1 at the Fukushima Daiichi site using different severe accident codes (ASTEC, MAAP, MELCOR, SAMPSON, THALES-KICHE). The present paper describes the findings of the comparison of the participants results for Unit 1 against each other and against plant data, the evaluation of the accident progression and the final status inside the reactors. Special focus is on RPV status, melt release and FP behaviour and release. Unit specific aspects will be highlighted and points of consensus as well as remaining uncertainties and data needs will be summarised. The results for Units 2 and 3, and an overall summary are presented in separated papers.
Original languageEnglish
Title of host publicationProceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18
PublisherAmerican Nuclear Society (ANS)
Pages1107-1118
Number of pages12
ISBN (Electronic)978-0-89448-767-5
Publication statusPublished - 2019
MoE publication typeA4 Article in a conference publication
Event18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Marriott Portland Downtown Waterfront, Portland, United States
Duration: 18 Aug 201923 Aug 2019

Conference

Conference18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
Abbreviated titleNURETH-18
Country/TerritoryUnited States
CityPortland
Period18/08/1923/08/19

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