年次大会講演論文集
Online ISSN : 2433-1325
セッションID: F-1705
会議情報
F-1705 原子力発電プラントの炉内構造物を対象とした応力拡大係数評価手法の検討(S59-2 規格基準の高度化に関連する研究・開発状況(2))(S59 規格基準の高度化に関連する研究・開発状況)
宮崎 克雅藤森 治男金澤 寧高橋 嘉明設楽 親
著者情報
会議録・要旨集 フリー

詳細
抄録
To verify the evaluation methods of stress intensity factor for a surface crack in a complex welded joint in the reactor internals of nuclear power plants, the stress intensity factors evaluated by two proposed methods were compared with those by finite element analysis (FEA). The stress intensity factors obtained by the first evaluation method (evaluation method 1) based on the influence function method were higher than those by three-dimensional (3D) FEA for a surface crack in the T-joint. To improve the accuracy of the evaluation method 1, the second evaluation method (evaluation method 2), which modifies with the ratio of geometry function evaluated by two-dimensional FEA was proposed. The stress intensity factors obtained by evaluation method 2 are in a good agreement with those by 3D FEA.
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© 2001 一般社団法人日本機械学会
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