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09413 Comparison of LPSCC Crack Tips of Alloy 132 and Alloy 600 – Influence of Dissolved Hydrogen –

Monday, March 23, 2009: 11:15 AM
C301 (Georgia World Congress Center)
Takumi Terachi , Institute of Nuclear Safety System, Incorporated, Fukui, Japan
Nobuo Totsuka , Institute of Nuclear Safety System, Incorporated, Fukui, Japan
Takuyo Yamada , Institute of Nuclear Safety System, Incorporated, Fukui, Japan
Tomoki Miyamoto , Institute of Nuclear Safety System, Incorporated, Fukui, Japan
Masayoshi Ozawa , Japan Nuclear Energy Safety Organization, Tokyo, Japan
Kiyotomo Nakata , Japan Nuclear Energy Safety Organization, Tokyo, Japan
Stress corrosion cracking of nickel based alloy has been reported in pressurized water reactors. To increase reliability of components, mechanistic studies for low-potential SCC on Alloy 600 and their weld were carried out using crack tip analyses technique.Crack tip samples were obtained from CT specimen examined under several dissolved hydrogen conditions. Analysis results indicate that a grain boundary oxidation seems to affect the LPSCC in hydrogenated condition, while no selective grainboundary oxidation observed in deaerated condition. In addition, dissolution of grainboundary carbide was discussed.
See more of: Corrosion in Nuclear Systems Session 1 - TEG 224X
See more of: Technical Symposium
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