ICONE11-36107 Stress corrosion cracking susceptibility of thermally sensitized type 304 stainless steels doped with various levels of carbon and silicon
スポンサーリンク
概要
著者
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TSUJI Hirokazu
Japan Atomic Energy Research Institute
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TSUKADA Takashi
Japan Atomic Energy Agency
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Miwa Yukio
Japan Atomic Energy Research Institute
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Tsuji Hirokazu
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
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Tsukada Takashi
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
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MIWA Yukio
Japan Atomic Energy Agency
関連論文
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- In-Core SCC Growth Behavior of Type 304 Stainless Steel in BWR Simulated High-Temperature Water at JMTR
- ICONE11-36136 Program of in-pile IASCC testing under the simulated actual plant condition : Development of Technique for In-pile IASCC Initiation Test in JMTR
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- ICONE11-36324 Program of in-pile IASCC testing under the simulated actual plant condition : Overview
- ICONE11-36111 Stress corrosion cracking susceptibility of thermally sensitized type 304 stainless steels doped with various levels of carbon and silicon
- ICONE11-36107 Stress corrosion cracking susceptibility of thermally sensitized type 304 stainless steels doped with various levels of carbon and silicon
- ICONE11-36093 AFM EVALUATION FOR CORROSION BEHAVIOR OF ION IRRADIATED STAINLESS STEEL
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- Creep Properties under Varying Stress/Temperature Conditions on Nickel-Base Heat-Resistant Alloy Hastelloy XR