FORMULATION OF THE IRRADIATION ASSISTED STRESS CORROSION CRACK GROWTH RATES FOR NEUTRON-IRRADIATED STAINLESS STEELS IN HIGH-TEMPERATURE WATER OF A BOILING WATER REACTOR

摘要

This study developed a simplified formula of theHashimoto-Koshiishi model for the calculation of crackgrowth rates of irradiated austenitic stainless steels toenable the practicable use of the model formula in theintegrity assessment of components. First, the inputparameters for the Hashimoto-Koshiishi model wereoptimized for irradiated type 316L stainless steels. Second,the simplified formulation was developed to reproduce themodel calculations of type 316L stainless steels.Calculated results were compared with experimental dataof type 316L and other types of irradiated stainless steels.There were good agreements between calculated andexperimental results.