Development of severe accident evaluation technology (Level 2 PSA) for sodium-cooled fast reactors (1) overview of evaluation methodology development

Ryodai Nakai, Tohru Suzuki, Hidemasa Yamano, Hiroshi Seino, Hiroyasu Ishikawa, Kenji Kamiyama, Kazuya Koyama, Koji Morita

Research output: Chapter in Book/Report/Conference proceedingConference contribution

12 Citations (Scopus)

Abstract

To consolidate the Probabilistic Safety Assessment (Level 2 PSA) for sodium-cooled fast reactors, the analytical methodologies in the core-material relocation phase and the ex-vessel accident sequence should be established. In addition, a technical basis for Level 2 PSA should also be built up to construct the phenomenological event trees and to determine the branch probabilities in them. In the present study, the analytical methodologies above have been developed with the aim of establishing a severe accident evaluation technology for sodium-cooled fast reactors, and the dominant factors in each phase have been identified through sensitivity analyses. The information obtained from these analyses will be effectively reflected on the technical basis which is indispensable for the construction of phenomenological event trees.

Original languageEnglish
Title of host publicationInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
PublisherAtomic Energy Society of Japan
Pages1110-1119
Number of pages10
ISBN (Electronic)9781617386084
Publication statusPublished - Jan 1 2009
EventInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 - Shinjuku, Tokyo, Japan
Duration: May 10 2009May 14 2009

Publication series

NameInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
Volume2

Other

OtherInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
CountryJapan
CityShinjuku, Tokyo
Period5/10/095/14/09

All Science Journal Classification (ASJC) codes

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering

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    Nakai, R., Suzuki, T., Yamano, H., Seino, H., Ishikawa, H., Kamiyama, K., Koyama, K., & Morita, K. (2009). Development of severe accident evaluation technology (Level 2 PSA) for sodium-cooled fast reactors (1) overview of evaluation methodology development. In International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 (pp. 1110-1119). (International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009; Vol. 2). Atomic Energy Society of Japan.