M&M材料力学カンファレンス
Online ISSN : 2424-2845
セッションID: OS0615
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BWR炉容器破損確率評価のためのPFMコード整備
*荒川 学町田 秀夫加藤 猛彦
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This paper describes the result of extension of the probabilistic fracture mechanics (PFM) cord PEPPER to evaluate the brittle fracture of the reactor pressure vessel (RPV) which did neutron irradiation embrittlement and shows the examination result. The analysis result were compared with the other PFM codes about the examination performed as the international round robin analysis phase 2 in PFM sub-committees in the Atomic Energy Research Committee of Japan Welding Engineering Society. The equivalent result was obtained with the other PFM codes and PEPPER code verification was performed.

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