M&M材料力学カンファレンス
Online ISSN : 2424-2845
セッションID: OS0813
会議情報
OS0813 原子炉圧力容器の健全性評価方法の高度化(1) : 日米の評価方法の比較と想定欠陥に関する検討
眞崎 浩一西川 弘之小坂部 和也勝山 仁哉鬼沢 邦雄
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会議録・要旨集 フリー

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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 provided for in the codes and standards. Authors have compared the assessment methods for RPV integrity under pressurized thermal shock in domestic and the United States. After reviewing the technical background of the structural integrity assessment method, we clarified the technical issues based on the latest knowledge in this field, and the differences of postulated crack treatments between domestic and the United States based on fracture mechanics analyses.

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© 2012 一般社団法人 日本機械学会
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