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Report No.

In-pile IASCC study in Japan Materials Testing Reactor, 2

Kaji, Yoshiyuki; Ugachi, Hirokazu; Matsui, Yoshinori; Tsukada, Takashi; Nagata, Nobuaki*; Dozaki, Koji*; Takiguchi, Hideki*

Irradiation assisted stress corrosion cracking (IASCC) is one of the critical concerns of in-core structural materials for light water reactors. In general, IASCC can be reproduced on the materials irradiated over a certain threshold fluence level of fast neutron by the post-irradiation examinations (PIEs). It is, however, considered that the reproduced IASCC by PIEs must be carefully compared with the actual IASCC in nuclear power plants, because the actual IASCC occurs in the core under simultaneous effects of radiation, stress and high temperature water environment. In this study, we conducted in-pile SCC growth tests in pure water simulated boiling water reactor (BWR) coolant condition and discussed comparing with the results obtained by PIEs from a viewpoint of the synergistic effects on IASCC.



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