M&M材料力学カンファレンス
Online ISSN : 2424-2845
セッションID: OS1417
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OS1417 原子炉格納容器試験体の弾塑性FEMを用いた解析評価
成田 慎太郎永田 徹也大坂 雅昭山崎 達広
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会議録・要旨集 フリー

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As one of responses to Fukushima event, structural integrity evaluation of Containment Vessel (CY) at severe accident has been promoted. This paper is intended to perform the elastic-plastic analysis of the pressure confirmatory testing of the Steel CV made in the past, to establish a method for analysis and evaluation at severe accident. Differences between test and analysis should be corrected using techniques ASME Sec. VIII which considers the effects of multiaxiality. Moreover, it is confirmed that the difference of equivalent plastic strain about 2.1 times between the test and analysis, caused by material discontinuities in the weld, for example. In ductile fracture assessment, it should be properly corrected this correction factor.
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© 2013 一般社団法人 日本機械学会
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