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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| Main Authors: | , , , , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
The Japan Society of Mechanical Engineers
2025-04-01
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| 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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