Fumihito HIROKAWA
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第10回
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
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:
キーワードタグ:
Boiling Water Reactor Fracture toughness Pressurized Thermal Shock Reactor Pressure Vessel Stress intensity factor Structural integrity Transient condition
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:
キーワードタグ:
Boiling Water Reactor Fracture toughness Pressurized Thermal Shock Reactor Pressure Vessel Stress intensity factor Structural integrity Transient condition
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. ...
英字タイトル:
Evaluation of Pressurized Thermal Shock in transitional condition for Boiling Water Reactor pressure vessel
英字タイトル:
Evaluation of Pressurized Thermal Shock in transitional condition for Boiling Water Reactor pressure vessel