神長 貴幸
著者に関連した記事は9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17回
BWR炉内構造物等点検評価ガイドライン 炉心シュラウド・ シュラウドサポートの改訂方針
著者:
三橋 忠浩,島津 忠昭,（東芝ESS）,小林 広幸,（日本原電）,菊川 浩,神長 貴幸,（東京電力）,椿 正昭,内山 好司,（日立GE）,佐藤 寿志,（原子力安全推進協会）
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BWR Core Shroud Inspection and Evaluation JANSI Guideline Reactor Internals Shroud Support
三橋 忠浩,島津 忠昭,（東芝ESS）,小林 広幸,（日本原電）,菊川 浩,神長 貴幸,（東京電力）,椿 正昭,内山 好司,（日立GE）,佐藤 寿志,（原子力安全推進協会）
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BWR Core Shroud Inspection and Evaluation JANSI Guideline Reactor Internals Shroud Support
The current edition of “Guideline of Inspection and Evaluation for Reactor Internals issued by Japan Nuclear Safety Institute (JANSI) consists of inspection target, inspection method, and evaluation. Recently, the guideline is revised based on the safety function of the Reactor Internals, domestic operation experience, and the new knowledge. In this report, summary of “Guidelines of Inspection and Evaluation for Reactor Internals [Core Shroud] and [Shroud Support]....
英字タイトル:
Guideline for BWR Inspection Program Revision Policy of Guidelines for Core Shroud and Shroud Support
英字タイトル:
Guideline for BWR Inspection Program Revision Policy of Guidelines for Core Shroud and Shroud Support
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
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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15回
RPV胴板の内部亀裂に対する構造健全性評価
著者:
板谷 雅雄,新川 嘉英,（東芝ESS）,神長 貴幸,（東京電力HD）
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Acceptable Crack Fatigue Crack Growth Internal Crack RPV Structural Integrity
板谷 雅雄,新川 嘉英,（東芝ESS）,神長 貴幸,（東京電力HD）
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Acceptable Crack Fatigue Crack Growth Internal Crack RPV Structural Integrity
When quasi-laminar defects are detected in the RPV shell, these defects are modeled to single circular crack with a diameter of 2a and an angle of ? from RPV wall enveloping these micro-defects like as the model used in the structural integrity assessment for Doel-3. An acceptable crack size is investigated for fracture assessment and initial crack size considering the fatigue crack growth by 60 years operation due to the JSME Fitness-for-Service (FFS) code. It was found that the initial crack with 2a of 4%...
英字タイトル:
Structural Integrity Assessment for Internal Crack in RPV Shell
英字タイトル:
Structural Integrity Assessment for Internal Crack in RPV Shell
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）
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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）
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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16回
監視試験片再生接合技術の実機適用性評価
著者:
田中 重彰,森島 康雄,小川 琢矢,服部 泰大,（東芝ESS）,和田 将樹,（日本核燃料開発）,神長 貴幸,（東京電力HD）
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Charpy impact test operation period extension reconstitution bonding RPV material surveillance test
田中 重彰,森島 康雄,小川 琢矢,服部 泰大,（東芝ESS）,和田 将樹,（日本核燃料開発）,神長 貴幸,（東京電力HD）
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Charpy impact test operation period extension reconstitution bonding RPV material surveillance test
In the application for approval of nuclear power plant operation period extension, it is required to carry out two surveillance tests separately from the conventional plan. At this time, it is necessary to compensate for the surveillance test piece by reconstitution bonding of the used test specimen, since the shortage of the test specimen is expected. Although the used test piece of the welded part is used for the reconstitution bonding of the heat affected zone (HAZ) test piece, the test piece collection ...
英字タイトル:
Applicability of Reconstituted Surveillance Test Piece for RPV Embrittlement Evaluation
英字タイトル:
Applicability of Reconstituted Surveillance Test Piece for RPV Embrittlement Evaluation
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
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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
第15回
電子ビーム溶接を用いて再生した衝撃試験片の監視試験への適用性評価
著者:
森島 康雄,小川 琢矢,（東芝ESS）,豊田 哲也,（日立GE）,石嵜 貴大,（日立製作所）,櫻谷 誠司,（日本核燃料開発）,神長 貴幸,（東京電力HD）
発刊日:
公開日:
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
森島 康雄,小川 琢矢,（東芝ESS）,豊田 哲也,（日立GE）,石嵜 貴大,（日立製作所）,櫻谷 誠司,（日本核燃料開発）,神長 貴幸,（東京電力HD）
発刊日:
公開日:
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 test are required to extend the operation license of nuclear power plants. Since the number of surveillance test specimens is limited, it is important to establish a reconstitution technique of the surveillance test specimen. Applicability evaluation of reconstituted impact test specimen by electron beam welding for RPV surveillance test were conducted, and it was confirmed that reconstituted impact test specimen was applicable to RPV surveillance test.
...
英字タイトル:
Applicability Evaluation of Reconstituted impact test specimen by electron beam welding for RPV Surveillance Test
英字タイトル:
Applicability Evaluation of Reconstituted impact test specimen by electron beam welding for RPV Surveillance Test