溶接部にき裂を有するステンレス鋼配管の破壊評価曲線

概要

論文の詳細を見る
The fracture assessment diagram approach is widely used to predict the fracture load or the critical crack size of nuclear components as in the ASME Code Case N-494. In this approach, a proper failure assessment curve must be defined to estimate fracture conditions accurately considering the effect of the thermal aging caused by long term operations. The present work deals with a crack located in the weldment of type 304 stainless steel pipes because of its higher susceptibility to the thermal aging than the base metal. So, the weldment was aged for 20,000 hours at 400℃ simulating long term operations of boiling water reactor (BWR) plants and was served to tests to obtain the mechanical properties of the aged weld metal. Using the stress-strain relationships of the unaged and aged metals, failure assessment curves are developed and compared with each other to make clear the effect of the thermal aging. Also the authors have checked the accuracy and conservatism of the curves stipulated in the R 6 approach and the ASME Code Case N-494 based on the present curve.
一般社団法人日本機械学会の論文
2001-07-25