Abstract
Abstract Intergranular stress corrosion cracking (IGSCC) susceptibility of irradiated, thermally sensitized type 304 (UNS S30400) stainless steels (SS) was studied as a function of neutron fluence and correlated with mechanical responses of the materials. Neutron irradiation was carried out to neutron fluences up to 5.4 × 1023 n/m2 (E > 1 MeV) at 290°C and to 1.1 × 1024 n/m2 (E > 1 MeV) at 340°C in the Japan Material Test Reactor. Irradiated specimens were examined by slow strain rate tensile testing (SSRT) in 290°C pure water of 0.2 ppm dissolved oxygen (DO) concentration, by SSRT at 290°C in argon gas, and by microhardness measurements. IGSCC susceptibility increased with neutron fluences up to 1.1 × 1024 n/m2 regardless of irradiation temperatures. The 0.2% proof stress (PS) and the grain-boundary (GBHV) and grain-center microhardness (GCHV) increased. The uniform elongation (UE) decreased with neutron fluences up to 5.4 × 1023 n/m2, but 0.2% PS and GBHV and GCHV decreased, and UE increased at 1.1 × 10...
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