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

摘要

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