廣川 文仁
著者に関連した記事は2件です。
更新情報
第15回
ライザーブレースアーム溶接部の構造健全性評価手法の検討
著者:
岩松 史則,廣川 文仁,（日立GE）,神長 貴幸,（東京電力HD）
発刊日:
公開日:
キーワードタグ:
and Crack Growth Evaluation Finite Element Analysis Fracture Mechanics Weld Residual Stress
岩松 史則,廣川 文仁,（日立GE）,神長 貴幸,（東京電力HD）
発刊日:
公開日:
キーワードタグ:
and Crack Growth Evaluation Finite Element Analysis Fracture Mechanics Weld Residual Stress
Flaw evaluation method for riser brace arm weld was investigated in case of a flaw is detected in in-service inspection. Weld residual stress was evaluated using 3-D finite element model considering structure of riser brace. Fatigue and SCC crack growth evaluation was performed using evaluated residual stress and stress due to normal operation. Two methods, which are JSME fitness-for-service code and influence function method, were applied to estimation of stress intensity factor to investigate effect of st...
英字タイトル:
Structural Integrity Assessment for Riser Brace Arm Weld
英字タイトル:
Structural Integrity Assessment for Riser Brace Arm Weld
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