Takayuki YAMADA
著者に関連した記事は2件です。
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第2回
SUS316L 鋼の表面残留応力に及ぼす機械加工の影響
著者:
中東 重雄,Shigeo NAKAHIGASHI,山本 厚之,Atsuyukitu YAMAMOTO,山田 孝行,Takayuki YAMADA,劉 莉,Lin LIU,寺澤 倫孝,Mititaka TERASAWA,三田村 徹,Tohru MITAMURA,椿野 晴繁,Harushige TSUBAKINO,菖蒲 敬久,Takahisa SHOBU,秋庭 義明,Yoshiaki AKINIWA
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SPring-8 stress corrosion cracking stress measurement SUS316L synchrotron radiation
中東 重雄,Shigeo NAKAHIGASHI,山本 厚之,Atsuyukitu YAMAMOTO,山田 孝行,Takayuki YAMADA,劉 莉,Lin LIU,寺澤 倫孝,Mititaka TERASAWA,三田村 徹,Tohru MITAMURA,椿野 晴繁,Harushige TSUBAKINO,菖蒲 敬久,Takahisa SHOBU,秋庭 義明,Yoshiaki AKINIWA
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SPring-8 stress corrosion cracking stress measurement SUS316L synchrotron radiation
Suppressing the stress corrosion cracking by reducing carbon contents in austenitic stainless steels seems to be not effective on core shrouds used in boiling water reactor in Japan. Trans-granul ar cracking was found out in the shrouds. To clarify a mechanism of the cracking, stress measurement on specimens under stretched condition in hot water has been attempted in the present study. A n in-situ device for diffraction measurements in synchrotron radiation facility has been developed by the present autho...
英字タイトル:
Effect of Surface Grinding on Residual Stress in Low Carbon Austenitic Stainless Steel SUS316L
英字タイトル:
Effect of Surface Grinding on Residual Stress in Low Carbon Austenitic Stainless Steel SUS316L
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. ...
英字タイトル:
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