Development of advanced PRA model for Shimane Unit 2 internal event at-power

An importance for risk management has come to be re-recognized in Japan after the accident of the Fukushima Daiichi nuclear power plants. A Probabilistic Risk Assessment (PRA) fulfills a significantly important role in the framework of the risk management. Technical adequacy of PRA model and high qu...

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主要な著者:	Yohei MORIYA, Kenichi IHARA, Hiroki NAKAMURA, Hitoshi NOJIMA, Satoshi YONEDA, Kenichi KANDA, Kozo MURAKAMI, Daichi SHIOTA, Naoki HIROKAWA
フォーマット:	Artigo
言語:	Inglês
出版事項:	The Japan Society of Mechanical Engineers 2024-02-01
シリーズ:	Mechanical Engineering Journal
主題:	probabilistic risk assessment (pra) risk informed decision making (ridm) fault tree (ft) analysis human reliability analysis (hra) core damage frequency (cdf) containment failure frequency (cff)
オンライン･アクセス:	https://www.jstage.jst.go.jp/article/mej/11/2/11_23-00414/_pdf/-char/en
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