加圧水型原子力発電所におけるニッケル基合金使用部に関する保全技術について
英字タイトル:
Maintenance Techniques on PWSCC of Ni Alloys Used as PWR Pressure Boundary Materials
著者:
伊藤 肇 Hajime ITO 平野 伸朗 Shinro HIRANO
発刊日:
公開日:
Alloy 600MaintenanceNuclear power plantPWSCCReactor vesselSteam generator
Maintenance Techniques on PWSCC of Ni Alloys Used as PWR Pressure Boundary Materials
著者:
伊藤 肇 Hajime ITO 平野 伸朗 Shinro HIRANO
発刊日:
公開日:
カテゴリ: 第3回
キーワードタグ:Alloy 600MaintenanceNuclear power plantPWSCCReactor vesselSteam generator
概要
Alloy 600, highly heat resistant and corrosion resistant, is widely used in nuclear power plant components, such as re actor pressure vessel nozzles and steam generator nozzles. However, some Alloy 600 components have recently experience d defects in Japan and abroad. In this regards, enhanced maintenance measures are required to deal with this problem. This paper describes representative defects; PWSCC in Alloy 600 components and summarizes countermeasures in advance.
