山田 浩二
著者に関連した記事は3件です。
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第10回
ステンレス鋼溶接金属を透過した超音波探傷試験
著者:
中川 純二,Junji NAKAGAWA,土屋 直柔,Naonari TSUCHIYA,菅原 良昌,Yoshimasa SUGAWARA,山田 浩二,Kouji YAMADA,西野 輝之,Teruyuki NISHINO,寺門 剛,Takeshi TERAKADO,木村 陸,Atsushi KIMURA,江原 和也,Kazuya EHARA,新川 嘉英,Yoshihide SHINKAWA,松田 誠司,Seiji MATSUDA
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Dissimilar Metal weld stainless steel Stress Corrosion Cracking crack through a stainless steel weld Ultrasonic Testing
中川 純二,Junji NAKAGAWA,土屋 直柔,Naonari TSUCHIYA,菅原 良昌,Yoshimasa SUGAWARA,山田 浩二,Kouji YAMADA,西野 輝之,Teruyuki NISHINO,寺門 剛,Takeshi TERAKADO,木村 陸,Atsushi KIMURA,江原 和也,Kazuya EHARA,新川 嘉英,Yoshihide SHINKAWA,松田 誠司,Seiji MATSUDA
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Dissimilar Metal weld stainless steel Stress Corrosion Cracking crack through a stainless steel weld Ultrasonic Testing
It is necessary to confirm the validity of crack detection by ultrasonic testing through a stainless steel weld in order to reduce a range impossible of detection by ultrasonic testing. Therefore, we performed ultrasonic testing used to specimen with various weld joint types for providing the basic data (probability and measurement accuracy) of ultrasonic testing methods to reflect on JEAC4207.As the result, ultrasonic testing used to longitudinal wave angle beam technique(including phased array techni...
英字タイトル:
Ultrasonic testing through stainless steel welds
英字タイトル:
Ultrasonic testing through stainless steel welds
第13回
原子炉圧力容器の給水ノズルコーナーに対する渦電流探傷技術の開発
著者:
神長 貴幸,Takayuki KAMINAGA,吉川 祐明,Hiroaki KIKKAWA,山田 浩二,Koji YAMADA,平崎 孝幸,Takayuki HIRASAKI,西岡 朋美,Tomomi NISHIOKA,首藤 浩丈,Hirotake SYUTOU,齋藤 康二,Koji SAITO,東海林 一,Hajime SHOHJI,江原 和也,Kazuya EHARA,土橋 健太郎,Kentaro TSUCHIHASHI
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Eddy current testing Fatigue crack Feed water nozzle inside corner Reactor pressure vessel
神長 貴幸,Takayuki KAMINAGA,吉川 祐明,Hiroaki KIKKAWA,山田 浩二,Koji YAMADA,平崎 孝幸,Takayuki HIRASAKI,西岡 朋美,Tomomi NISHIOKA,首藤 浩丈,Hirotake SYUTOU,齋藤 康二,Koji SAITO,東海林 一,Hajime SHOHJI,江原 和也,Kazuya EHARA,土橋 健太郎,Kentaro TSUCHIHASHI
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Eddy current testing Fatigue crack Feed water nozzle inside corner Reactor pressure vessel
It is necessary to confirm whether the feed water nozzle inside corner has crack by eddy current testing, to enable long-term operation of a plant. Therefore, we performed eddy current testing using various types of specimen to collect basic data (probability and length measurement accuracy) of the eddy current testing methods, complying with JEAG4217. As a result, eddy current testing was effective for the inspection of feed water nozzle inside corner. ...
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Eddy current testing technique for feed water nozzle inside corner of nuclear reactor pressure vessel
英字タイトル:
Eddy current testing technique for feed water nozzle inside corner of nuclear reactor pressure vessel
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
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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
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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