Effects of water and irradiation temperatures on IASCC susceptibility of type 316 stainless steel
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Evaluation of irradiation assisted stress corrosion cracking (IASCC) of type 316 stainless steel irradiated in FBR
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3. Irradiation-assisted SCC susceptibility of HIPed 316LN-IG stainless steel irradiated at 473 K to 1 dpa
4. Stress corrosion cracking of AISI 316LN stainless steel in ITER primary water conditions
5. Effect of irradiation temperature on irradiation assisted stress corrosion cracking of model austenitic stainless steels
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4. SCC behavior of solid-HIPed and irradiated type 316LN-IG stainless steel in oxygenated or hydrogenated water at 423–603K;Journal of Nuclear Materials;2007-08
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