沸騰水型原子炉圧力容器の過渡事象における 加圧熱衝撃の評価
英字タイトル:
Evaluation of Pressurized Thermal Shock in transitional condition for Boiling Water Reactor pressure vessel
著者:
桝田 祐貴 Yuki MASUDA 高橋 淳介 Junsuke TAKAHASHI 廣川 文仁 Fumihito HIROKAWA 山田 浩二 Koji YAMADA
発刊日:
公開日:
Boiling Water ReactorFracture toughnessPressurized Thermal ShockReactor Pressure VesselStress intensity factorStructural integrityTransient condition
Evaluation of Pressurized Thermal Shock in transitional condition for Boiling Water Reactor pressure vessel
著者:
桝田 祐貴 Yuki MASUDA 高橋 淳介 Junsuke TAKAHASHI 廣川 文仁 Fumihito HIROKAWA 山田 浩二 Koji YAMADA
発刊日:
公開日:
カテゴリ: 第10回
キーワードタグ:Boiling Water ReactorFracture toughnessPressurized Thermal ShockReactor Pressure VesselStress intensity factorStructural integrityTransient condition
概要
The structural integrity for Pressurized Thermal Shock (PTS) was evaluated for the RPVs of Japanese Boiling Water Reactors (BWRs). It has been clarified that the BWR RPVs have the sufficient margin of fracture toughness by calculating the stress intensity factor in transitional condition and the acceptance criteria for RPV shell plate which is assumed to be neutron-irradiated in core region for 60 years.
