抄録
Austenitic stainless steels are used as internals of Boling Water Reactor (BWR). The internal components are exposed to neutron irradiation and high-temperature reactor water. Irradiation and the water environment reduce the resistance to stress corrosion cracking. It is important for stable operation with a high level of safety to adequately evaluate structural integrity for irradiation assisted stress corrosion cracking (IASCC). IASCC evaluation guide for BWR core internals was issued to evaluate the IASCC crack propagation, irradiation-induced creep relaxation and fracture toughness. However, it is expected that it may be with a conservative evaluation excessively according to IASCC evaluation guide. In this report, residual stress relaxation by irradiation for core shroud weld is calculated by using FEM.
