SCC behavior of solid-HIPed and irradiated type 316LN-IG stainless steel in oxygenated or hydrogenated water at 423–603 K

Effects of water temperature on the stress corrosion cracking (SCC) susceptibility were studied on a solid hot-isostatic pressed (solid-HIPed) type 316LN-ITER grade (316LN-IG) stainless steel in unirradiated or irradiated condition. Neutron irradiation was conducted at a nominal temperature of 473 K...

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Bibliographic Details
Published in:Journal of nuclear materials 2007-08, Vol.367, p.1175-1179
Main Authors: Miwa, Yukio, Tsukada, Takashi, Jitsukawa, Shiro
Format: Article
Language:English
Subjects:
Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Installations for energy generation and conversion: thermal and electrical energy
Online Access:Get full text
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Summary:Effects of water temperature on the stress corrosion cracking (SCC) susceptibility were studied on a solid hot-isostatic pressed (solid-HIPed) type 316LN-ITER grade (316LN-IG) stainless steel in unirradiated or irradiated condition. Neutron irradiation was conducted at a nominal temperature of 473 K to a dose level of 1 dpa. Slow strain rate testing (SSRT) was performed over a temperature range from 423 to 603 K in oxygenated (DO = 10 ppm) or hydrogenated (DH = 1 ppm) water. In the unirradiated condition, intergranular (IG) type SCC occurred at 603 K in the oxygenated and in the hydrogenated water. In the irradiated condition, IASCC occurred above 573 K in oxygenated water. In the hydrogenated water, IASCC occurred at 513 K, but was suppressed at 573 K.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2007.03.210