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Sensitive Analyses of Probabilistic Fracture Mechanics for Reactor Pressure Vessel during Pressurized Thermal Shock and Comparison with the Results of International Round Robin Analyses in Asian Countries

机译：加压热冲击过程中反应堆压力容器概率断裂力学的敏感性分析及与亚洲国家国际循环分析结果的比较

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摘要

This paper demonstrates sensitive analyses of probabilistic fracture mechanics (PFM) for reactor pressure vessel (RPV) during pressurized thermal shock (PTS) loading, and comparison of our calculation with the results of the international round robin (RR) analyses in Asian countries (Korea, Taiwan and Japan). The international Round Robin activity was performed in PFM sub-committees in the Atomic Energy Research Committee of Japan Welding Engineering Society (JWES) in conjunction with Korea and Taiwan research groups. The purposes of this program are to establish reliable procedures to evaluate fracture probability of reactor pressure vessels during pressurized thermal shock and to maintain the continuous cooperation among Asian institutes in the probabilistic approach to nuclear safety. Some parameters to RPV failure probabilities are chosen to evaluate their significance quantatively. The differences caused by selection of analyzing programs and some input parameters will be discussed.
机译：本文展示了加压热冲击（PTS）加载期间反应堆压力容器（RPV）的概率断裂力学（PFM）的敏感分析，并将我们的计算结果与亚洲国家（韩国）的国际循环法（RR）分析结果进行了比较，台湾和日本）。国际循环活动是在日本焊接工程学会（JWES）原子能研究委员会的PFM小组委员会中与韩国和台湾研究小组一起进行的。该计划的目的是建立可靠的程序，以评估加压热冲击过程中反应堆压力容器的破裂可能性，并维持亚洲机构之间在概率安全性核方法方面的持续合作。选择一些RPV失败概率参数来定量评估其重要性。将讨论由分析程序的选择和一些输入参数引起的差异。

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