Hideya ANZAI
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BWR環境下で長期間使用されたニッケル基合金の応力腐食割れ
著者:
青木 孝行,Takayuki AOKI,服部 成雄,Shigeo HATTORI,安齋 英哉,Hideya ANZAI,住本 秀樹,Hideki SUMIMOTO
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aging degradation Boiling water reactor long time service Ni-base alloy stress corrosion cracking
青木 孝行,Takayuki AOKI,服部 成雄,Shigeo HATTORI,安齋 英哉,Hideya ANZAI,住本 秀樹,Hideki SUMIMOTO
発刊日:
公開日:
キーワードタグ:
aging degradation Boiling water reactor long time service Ni-base alloy stress corrosion cracking
In recent years, several cases have been reported that SCC was found in reac- tor internals and reactor nozzle safe-end and penetrations of BWR. Therefore, it is getting more important to understand what kind of characteristics Ni-base alloy used for a long time in BWR have. In this study, the results of the investiga- tion on SCC found in the shroud support (Ni-base alloy) of the oldest BWR in Japan, Tsuruga unit 1, in 1999 are discussed. Based on the discussion, the conclusions are summarized as fol...
英字タイトル:
Stress Corrosion Cracking in Ni-base Alloy Used for a Long Time in a BWR
英字タイトル:
Stress Corrosion Cracking in Ni-base Alloy Used for a Long Time in a BWR