材料力学部門講演会講演論文集
Online ISSN : 2433-1287
会議情報
607 原子炉圧力容器の破壊評価曲線
浅野 政之深倉 寿一菊池 正明
著者情報
会議録・要旨集 フリー

p. 443-444

詳細
抄録
This paper describes failure assessment curves of a pressure vessel of boiling water reactor containing a longitudinal surface crack at an inner surface. The failure assessment curves are derived from the J-integral based on the deformation theory of plasticity using the stress-strain curves of low alloy steel A508cl.3. The authors have made clear the dependence of failure assessment curve on crack geometry and compared with the curve for ferritic steel pipes given in the ASME Code Case N-494. Detail discussions are shown in the following.
著者関連情報
© 2000 一般社団法人日本機械学会
前の記事 次の記事
feedback
Top