TY - JOUR
T1 - 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 2
AU - Sonnenkalb, M.
AU - Pellegrini, M.
AU - Herranz, L. E.
AU - Lind, T.
AU - Morreale, A. C.
AU - Kanda, K.
AU - Tamaki, H.
AU - Kim, S. I.
AU - Cousin, F.
AU - Fernandez Moguel, L.
AU - Andrews, N.
AU - Sevon, Tuomo
PY - 2020/12/1
Y1 - 2020/12/1
N2 - This is the second paper in a series of 3 in which results of severe accident analyses for Unit 2 of Fukushima Daiichi are presented, gained in phase 2 of the OECD/NEA project “Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF)”. Nine organizations of six countries (CNL Canada; CRIEPI, IAE, JAEA and NRA Japan; IRSN France; KAERI Korea; NRC/DOE/SNL U.S. and VTT Finland) submitted results of their calculated severe accident scenarios for Unit 2 of Fukushima Daiichi 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 2 against each other and against plant data, the evaluation of the accident progression and the final status inside the reactors. Special focus is on reactor pressure vessel status, melt release and fission product behavior and release. Unit 2 specific aspects will be highlighted and points of consensus as well as remaining uncertainties and data needs will be summarized.
AB - This is the second paper in a series of 3 in which results of severe accident analyses for Unit 2 of Fukushima Daiichi are presented, gained in phase 2 of the OECD/NEA project “Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF)”. Nine organizations of six countries (CNL Canada; CRIEPI, IAE, JAEA and NRA Japan; IRSN France; KAERI Korea; NRC/DOE/SNL U.S. and VTT Finland) submitted results of their calculated severe accident scenarios for Unit 2 of Fukushima Daiichi 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 2 against each other and against plant data, the evaluation of the accident progression and the final status inside the reactors. Special focus is on reactor pressure vessel status, melt release and fission product behavior and release. Unit 2 specific aspects will be highlighted and points of consensus as well as remaining uncertainties and data needs will be summarized.
KW - Fukushima Daiichi NPP
KW - OECD/NEA BSAF project
KW - Severe accident analyses
KW - Unit 2
UR - http://www.scopus.com/inward/record.url?scp=85092285941&partnerID=8YFLogxK
U2 - 10.1016/j.nucengdes.2020.110840
DO - 10.1016/j.nucengdes.2020.110840
M3 - Article
AN - SCOPUS:85092285941
SN - 0029-5493
VL - 369
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 110840
ER -