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Seismic PRA for Japan Sodium-cooled Fast Reactor (JSFR)

JSFRに対する地震PRA

鳴戸 健一*; 西野 裕之 ; 栗坂 健一 ; 山野 秀将  ; 岡野 靖; 岡村 茂樹*; 衛藤 将生*

Naruto, Kenichi*; Nishino, Hiroyuki; Kurisaka, Kenichi; Yamano, Hidemasa; Okano, Yasushi; Okamura, Shigeki*; Eto, Masao*

Seismic Probabilistic Risk Assessment (PRA) is increasingly important in assessing the safety of nuclear power plants after the TEPCO's Fukushima Daiichi Nuclear Power Station accident. In this study, a seismic PRA under a rated power operation was performed for Japan Sodium cooled Fast Reactor (JSFR) developed by Japan Atomic Energy Agency. This PRA was intended to examine seismic impacts on the JSFR by calculating the Core Damage Frequency (CDF) with the identification of all the accident sequences induced by earthquake which may have potential possibility of direct core damage. Seismic hazard data was based on assessment results for existing nuclear site locations in Japan. Seismic fragility needed to quantify the accident sequences was set based on existing assessments for similar equipment. The base-case analysis showed that the total CDF would be approximately 10$$^{-6}$$ /reactor-year and JSFR is robust against the earthquake in the range of this assessment. The dominant contributor (about 80%) to the CDF is direct core damage by the sequence of simultaneous failures of reactor vessel and guard vessel. Sensitivity analysis was performed focusing on the simultaneous failures of reactor vessel and guard vessel. This result suggested that enhancement of failure probability assessment for guard vessels and/or provision of measures for maintaining coolant level following reactor vessel failure would be effective to reduce the CDF.

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