Takayuki KAMINAGA
著者に関連した記事は4件です。
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第14回
BWRプラントにおける 上部格子板の照射誘起応力腐食割れ評価の適正化
著者:
三橋 忠浩,Tadahiro MITSUHASHI,服部 泰大,Yasuhiro HATTORI,大木 俊,Suguru OOKI,神長 貴幸,Takayuki KAMINAGA,渡辺 義雄,Yoshio WATANABE,内山 好司,Koji UCHIYAMA
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BWR Core Components IASCC PLM PSR Top Guide
三橋 忠浩,Tadahiro MITSUHASHI,服部 泰大,Yasuhiro HATTORI,大木 俊,Suguru OOKI,神長 貴幸,Takayuki KAMINAGA,渡辺 義雄,Yoshio WATANABE,内山 好司,Koji UCHIYAMA
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BWR Core Components IASCC PLM PSR Top Guide
As for BWR, Core components made of austenitic stainless steels where IASCC is assumed are Top Guide, Core Shroud and Core Plate. Since Top Guide has been exposed to high flux of neutron irradiation during plant operation, the evaluation method should be established using reasonable and proper evaluation conditions. Based on this background, study on evaluation method for Top Guide was performed in this research as described below. ...
英字タイトル:
Optimizing evaluation method of irradiation-assisted stress corrosion cracking in Top Guide of BWR
英字タイトル:
Optimizing evaluation method of irradiation-assisted stress corrosion cracking in Top Guide of BWR
第14回
RPV 監視試験片の再生方法における 電子ビーム溶接の適用性評価
著者:
山岡 鉄史,Tetsushi YAMAOKA,森島 康雄,Yasuo MORISHIMA,小川 琢矢,Takuya OGAWA,豊田 哲也,Tetsuya TOYOTA,石嵜 貴大,Takahiro ISHIZAKI,櫻谷 誠司,Seiji SAKURAYA,神長 貴幸,Takayuki KAMINAGA,大木 俊,Suguru OOKI
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Charpy impact test Electron beam welding Low alloy steel Reactor pressure vessel Reconstitution method of test specimen Surveillance test
山岡 鉄史,Tetsushi YAMAOKA,森島 康雄,Yasuo MORISHIMA,小川 琢矢,Takuya OGAWA,豊田 哲也,Tetsuya TOYOTA,石嵜 貴大,Takahiro ISHIZAKI,櫻谷 誠司,Seiji SAKURAYA,神長 貴幸,Takayuki KAMINAGA,大木 俊,Suguru OOKI
発刊日:
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キーワードタグ:
Charpy impact test Electron beam welding Low alloy steel Reactor pressure vessel Reconstitution method of test specimen Surveillance test
Additional RPV surveillance tests are required to extend the operation license of nuclear power plants under the new regulation. Since the number of surveillance test specimens is limited, it is important to establish a reconstitution technique of the surveillance test specimen using the remaining undeformed part of the tested specimen. To evaluate the applicability of electron beam welding, the confirmatory tests such as Charpy impact tests were conducted using unirradiated test specimens reconstituted ...
英字タイトル:
Evaluating the Applicability of Electron Beam Welding to Reconstitution Method of RPV Surveillance Test Specimen
英字タイトル:
Evaluating the Applicability of Electron Beam Welding to Reconstitution Method of RPV Surveillance Test Specimen
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
第13回
軽水炉プラント停止期間中における Ni 基合金溶接金属の SCC 亀裂進展可能性評価
著者:
酒井 裕介,Yusuke SAKAI,熊谷 克彦,Katsuhiko KUMAGAI,深谷 祐一,Yuichi FUKAYA,神長 貴幸,Takayuki KAMINAGA
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Light-water reactor Ni base weld metal SCC SCC growth rate
酒井 裕介,Yusuke SAKAI,熊谷 克彦,Katsuhiko KUMAGAI,深谷 祐一,Yuichi FUKAYA,神長 貴幸,Takayuki KAMINAGA
発刊日:
公開日:
キーワードタグ:
Light-water reactor Ni base weld metal SCC SCC growth rate
Experimental evaluations were conducted to verify whether the significant SCC growth is possible or not in Ni base weld metals during cold shutdown period of light-water reactors. As a result, it has been confirmed that the SCC growth rate decreases with decreasing temperature and the growth rate below 100 °C is low enough to be neglected in plant evaluations. ...
英字タイトル:
Evaluation of SCC growth susceptibility of Ni base alloy weld metal during the shutdown period of Light-water reactors
英字タイトル:
Evaluation of SCC growth susceptibility of Ni base alloy weld metal during the shutdown period of Light-water reactors