OS2505 BWRプラントのIASCCき裂進展に対する健全性評価手法の検討 : (1)炉心シュラウド溶接部の照射による残留応力緩和評価(OS25-2 応力腐食割れ・配管,OS-25 供用エネルギー機器の経年変化と健全性評価)

概要

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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.
一般社団法人日本機械学会の論文
2011-07-16