IRRADIATION-ASSISTED STRESS CORROSION CRACKING OF TI-STABILIZED AUSTENITIC STAINLESS STEEL

摘要

IASCC has been widely observed in reactor vessel internals (RVI) in BWRs and pressurized water PWRs of the western type. In the eastern type of PWRs, also called WWERs, IASCC has been reported in only a few cases. The main differences between the PWRs of western and eastern designs are the construction materials of RVI (Type 321 in WWERs) and the operational environment. New crack growth disposition curves for RVI materials in PWR of western type (the proposed 75th percentile PWR curve in the ASME Section XI Code Case N-889, and the PWR mean curve) were used to verify the curves applicability also for RVI materials in WWERs.