Development of enhanced PRA model for Shimane Unit 2 internal event at-power for reflecting new findings including current plant states

After the Fukushima Daiichi nuclear power plants accident, the scope of Probabilistic Risk Assessment (PRA) application was enhanced to meet the new Japanese regulatory standard for nuclear power plants. In addition to that, an importance for risk management has come to be re-recognized in Japan. To...

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Bibliographic Details
Main Authors: Takahiro USUI, Hiroki NAKAMURA, Kenichi IHARA, Hitoshi NOJIMA, Kenichi KANDA, Kazunobu NORIYASU, Daichi SHIOTA, Naoki HIROKAWA
Format: Article
Language:English
Published: The Japan Society of Mechanical Engineers 2025-04-01
Series:Mechanical Engineering Journal
Subjects:
Online Access:https://www.jstage.jst.go.jp/article/mej/12/4/12_24-00439/_pdf/-char/en
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