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Technical review of structural integrity assessment procedure on reactor pressure vessel, 1; Comparison of procedures in Japan and U.S. and study on the postulated flaw

Masaki, Koichi; Nishikawa, Hiroyuki*; Osakabe, Kazuya*; Katsuyama, Jinya  ; Onizawa, Kunio 

The structural integrity of a reactor pressure vessel (RPV) should be maintained to ensure the safe long-term operation of a nuclear power plant. The assessment methods for RPV integrity are stipulated in the codes and standards. We compared the assessment methods for RPV integrity under pressurized thermal shock events in Japan and the United States. After reviewing the technical background of the assessment method, we clarified the technical issues based on the latest knowledge in this field. We also identified based on sensitivity analysis that a postulated crack which is provided in the domestic code was more conservative than that of the United States.

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