Irradiation assisted stress corrosion cracking (IASCC) is one of the environmental degradation problems of in-core structural materials for light water reactors. The effects of irradiation and water temperatures on the IASCC were studied using type 316(LN) stainless steels irradiated at 333-673 K to 1.1-16 dpa. IASCC did not occur at 513 K in oxygenated water for specimens irradiated below 573 K to 1.1-16 dpa, but IASCC occurred above 533 K in oxygenated water for all specimens. The irradiation temperature had a strong influence on IASCC susceptibility at 513 K in oxygenated water, so that the irradiation temperature dependence was compared with the temperature dependence of other radiation-induced phenomena.
Language |
: | English |
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Number |
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Pages |
: | p.161 - 168 |
Publication Year/Month |
: | 2004/10 |
Meeting title |
: | 8th Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering |
Held date |
: | 2004/10 |
Location (city) |
: | Sendai |
Location (country) |
: | Japan |
Paper URL |
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Keywords |
: | IASCC; Stainless Steel; Neutron Irradiation; Irradiation Temperature; Water Temperature; Slow Strain Rate Testing |
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