Correlation between oxide film and stress corrosion cracking susceptibility of surface cold worked L-grade stainless steels

被引:0
|
作者
Obata, Ryoji [1 ]
Koshiishi, Masato [1 ]
Anzai, Hideya [2 ]
Nakade, Katsuyuki [3 ]
Ooki, Suguru [3 ]
Takamori, Kenro [3 ]
Suzuki, Shunichi [3 ]
机构
[1] Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, 319-0073, Japan
[2] Materials Research Laboratory, Hitachi, Ltd., Hitachi, Ibaraki, 319-1292, Japan
[3] Tokyo Electric Power Company, Yokohama, Kanagawa, 230-8510, Japan
来源
14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 | 2009年 / 1卷
关键词
Compilation and indexing terms; Copyright 2024 Elsevier Inc;
D O I
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中图分类号
学科分类号
摘要
Tensile strain - Residual stresses - Cracks - Film growth - Oxide films - Stainless steel - Boiling water reactors - Nuclear fuels - Steel corrosion
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页码:622 / 635
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