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
著者:
勝又 源七郎 Genshichiro KATSUMATA 眞崎 浩一 Koichi MASAKI 小坂部 和也 Kazuya OSAKABE 西川 弘之 Hiroyuki NISHIKAWA 勝山 仁哉 Jinya KATSUYAMA 西山 裕孝 Yutaka NISHIYAMA 鬼沢 邦雄 Kunio ONIZAWA
発刊日:
公開日:
Fracture ProbabilityFracture ToughnessIrradiation EmbrittlementPostulated CrackPressurized Thermal ShockProbabilistic Fracture MechanicsReactor Pressure VesselStructural Integrity
概要
To assure the structural integrity of a reactor pressure vessel (RPV) is known as one of the critical issu es 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 h ave initiated extensive research on the improvement of structural integrity assessment methods of RPVs. I this paper, we describe some research results obtained from the second-year activity. These include the st udy on revisiting the technical background of the methods, such as loading conditions, postulated crack de finition, the other evaluation methods. In addition, studies on probabilistic methods for the applicabilit y to the current rules and the standardization of the probabilistic analysis methods have been presented.
