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• W3123025207 abstract "The irradiated microstructure and irradiation-assisted stress corrosion cracking (IASCC) susceptibility were determined for neutron-irradiated cold-worked (CW) 316 stainless steel tested in 320 °C simulated PWR primary water with various damage levels of 46.9, 67.4, and 125.4 dpa. The size and density of dislocation loops and precipitates were found to vary little over the dose range 46.9–125.4 dpa and dislocation loops were found to control the irradiation hardening. The %IG in constant extension rate tensile (CERT) tests and the stress to initiate a crack in four-point bend tests were consistent in establishing that the IASCC susceptibility was essentially unchanged across the dpa range. GB oxidization was observed prior to crack initiation, and localized deformation and triple junctions where local stresses were high were preferred crack initiation sites. IASCC cracks initiated preferentially on grain boundaries oriented nearly normal to the applied stress. An apparent threshold stress threshold for IASCC was determined to be ~45% of the irradiated yield strength for neutron-irradiated CW 316 SS between 46.9 and 125.4 dpa. • The IASCC susceptibility of cold-worked 316 SS showed only a slight dependence on damage level in the range 46.9 to 125.4 dpa. • Grain boundary oxidization often occurs prior to crack initiation and is a likely precursor condition to cracking. • The apparent stress threshold for IASCC crack initiation of neutron-irradiated cold-worked 316SS in PWR primary water at 320 °C is ~45% of the irradiated yield strength." @default.
• W3123025207 created "2021-02-01" @default.
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• W3123025207 date "2021-03-01" @default.
• W3123025207 modified "2023-10-10" @default.
• W3123025207 title "IASCC of neutron irradiated 316 stainless steel to 125 dpa" @default.
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• W3123025207 doi "https://doi.org/10.1016/j.matchar.2021.110897" @default.
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