SCC growth behavior of type 304 stainless steel irradiated under the different dose rates at JMTR

Tsukada, Takashi ; Kaji, Yoshiyuki  ; Ugachi, Hirokazu ; Nakano, Junichi; Kondo, Keietsu  ; Arai, Kensaku*; Nakata, Kiyotomo*

In order to investigate the effect of neutron dose rate on the mechanical property and stress corrosion cracking (SCC) growth behavior of type 304 stainless steel, the crack growth rate (CGR) test, tensile test and microstructure observation have been conducted after neutron irradiation. The specimens were irradiated up to about 1dpa with different dose rates in the Japan Materials Testing Reactor (JMTR). The radiation hardening increased with the high dose rate condition, and a little difference of radiation-induced segregation at grain boundaries was observed in specimens irradiated by different dose rates. There was no remarkable effect of dose rates on IASCC growth behavior.