Development of the evaluation method of IASCC initiation susceptibility for the proton-irradiated stainless steels

摘要

Irradiation-assisted stress corrosion cracking(IASCC)of the reactor internal materials such as the type 304 and 316 stainless steels has been researched significantly for the long-term operation of the nuclear power plants since some cracks were detected on the baffle former bolts or guide tube support pins.In this research,IASCC initiation susceptibility was evaluated for the proton-irradiated type 316 stainless steels.