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

研究成果: Chapter in Book/Report/Conference proceedingConference contribution

12 引用 (Scopus)

抜粋

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.

元の言語英語
ホスト出版物のタイトルInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
出版者Atomic Energy Society of Japan
ページ1110-1119
ページ数10
ISBN(電子版)9781617386084
出版物ステータス出版済み - 1 1 2009
イベントInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 - Shinjuku, Tokyo, 日本
継続期間: 5 10 20095 14 2009

出版物シリーズ

名前International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
2

その他

その他International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
日本
Shinjuku, Tokyo
期間5/10/095/14/09

All Science Journal Classification (ASJC) codes

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering

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  • これを引用

    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. : 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; 巻数 2). Atomic Energy Society of Japan.