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

التفاصيل البيبلوغرافية
العنوان: 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
المؤلفون: Luis Enrique Herranz, Marco Pellegrini, Terttaliisa Lind, Martin Sonnenkalb, Godin-Jacqmin, L., Claudia López, Dolganov, K., Cousin, F., Tamaki, H., Kim, T. W., Hoshi, H., Nathan Andrews, Tuomo Sevón
المصدر: Herranz, L E, Pellegrini, M, Lind, T, Sonnenkalb, M, Godin-Jacqmin, L, López, C, Dolganov, K, Cousin, F, Tamaki, H, Kim, T W, Hoshi, H, Andrews, N & Sevon, T 2019, 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 . in Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18 ., 29243, American Nuclear Society (ANS), pp. 1107-1118, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, Portland, Oregon, United States, 18/08/19 .
VTT Technical Research Centre of Finland-PURE
Tuomo Sevón
بيانات النشر: American Nuclear Society (ANS), 2019.
سنة النشر: 2019
الوصف: 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.
اللغة: English
URL الوصول: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::3dc04b43a02c92edb7174e880a2eeaea
https://cris.vtt.fi/en/publications/d933bf78-4c3d-4bb5-aba2-214c2609d2ba
حقوق: RESTRICTED
رقم الأكسشن: edsair.dedup.wf.001..3dc04b43a02c92edb7174e880a2eeaea
قاعدة البيانات: OpenAIRE