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高経年化技術評価の高度化-原子炉圧力容器の健全性評価-

Study of system safety evaluation on LTO of National project structural integrity assessment of reactor pressure vessels

勝又 源七郎; 眞崎 浩一*; 小坂部 和也*; 西川 弘之*; 勝山 仁哉; 西山 裕孝; 鬼沢 邦雄

Katsumata, Genshichiro; Masaki, Koichi*; Osakabe, Kazuya*; Nishikawa, Hiroyuki*; Katsuyama, Jinya; Nishiyama, Yutaka; Onizawa, Kunio

原子炉圧力容器(RPV)の構造健全性を保証することは、原子力発電所の安全な長期供用を維持するために重要な課題の一つである。原子力機構はこのRPVの構造健全性評価手法の高度化について研究を進めており、健全性評価において想定すべき荷重条件、き裂伝播停止靱性、その他の高経年化にかかわる評価法についての調査や、炉心領域部以外の部位に対する評価法の調査、さらに健全性評価に対する確率論的評価手法の適用性の確認及び標準化に向けた検討を行っている。本稿では、これらの調査研究について平成24年度に得られた成果の概要を示す。

To assure the structural integrity of a reactor pressure vessel (RPV) is known as one of the critical issues to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment methods for RPV integrity, stipulated in the codes and standards, have been endorsed by the regulatory body. Authors have initiated extensive research on the improvement of structural integrity assessment methods of RPVs. In this paper, we describe some research results obtained from the second-year activity. These include the study on revisiting the technical background of the methods, such as loading conditions, postulated crack definition, the other evaluation methods. In addition, studies on probabilistic methods for the applicability to the current rules and the standardization of the probabilistic analysis methods have been presented.

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