清水 禎人
著者に関連した記事は4件です。
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第2回
3WR炉内構造物のニッケル基合金溶接部に発見された応力腐食割れの超音波探傷試験結果とその評価
著者:
青木 孝行,Takayuki AOKI,小林 広幸,Hiroyuki KOBAYSHI,樋口 真一,Shinichi HIGUCHI,清水 禎人,Sadato SHIMIZU
発刊日:
公開日:
キーワードタグ:
Boiling Water Reactor Ni-base Alloy Stress Corrosion Cracking TOFD Ultrasonic Examination
青木 孝行,Takayuki AOKI,小林 広幸,Hiroyuki KOBAYSHI,樋口 真一,Shinichi HIGUCHI,清水 禎人,Sadato SHIMIZU
発刊日:
公開日:
キーワードタグ:
Boiling Water Reactor Ni-base Alloy Stress Corrosion Cracking TOFD Ultrasonic Examination
A Ni-base alloy weld, including cracks due to stress corrosion cracking found in the reactor internal of the oldest BWR in Japan, Tsuruga unit 1, in 1999, was examined by three (3) types of UT method. After this examination, a depth of each crack was confirmed by carrying out a little excavation with a grinder and PT examination by turns until each crack Hisappeared. Then, the depth measured by the former method was comp ared with the one measured by the latter method. n this fashion, performances of the ...
英字タイトル:
Evaluation on Ultrasonic Examination Methods applied to Ni-base Alloy Weld including Cracks dueto Stress Corrosion Cracking found in BWR Reactor Internal
英字タイトル:
Evaluation on Ultrasonic Examination Methods applied to Ni-base Alloy Weld including Cracks dueto Stress Corrosion Cracking found in BWR Reactor Internal
論文
BWR環境下で長期間使用されたニッケル基合金溶接部の応力腐食割れ事象から得られた知見に基づくき裂進展解析評価
著者:
青木 孝行,Takayuki AOKI,清水 禎人,Sadato SHIMIZU,宮崎 克雅,Katsumasa MIYAZAKI,林 正明,Masaaki HAYASHI,小林 広幸,Hiroyuki KOBAYASHI
発刊日:
公開日:
キーワードタグ:
Alloy 182 Aspect Ratio Crack Growth Analysis Crack Model Ni-based Alloy Residual Stress Stress Analysis Stress Corrosion Cracking
青木 孝行,Takayuki AOKI,清水 禎人,Sadato SHIMIZU,宮崎 克雅,Katsumasa MIYAZAKI,林 正明,Masaaki HAYASHI,小林 広幸,Hiroyuki KOBAYASHI
発刊日:
公開日:
キーワードタグ:
Alloy 182 Aspect Ratio Crack Growth Analysis Crack Model Ni-based Alloy Residual Stress Stress Analysis Stress Corrosion Cracking
During the field work of the core shroud replacement project of Tsuruga power station unit 1 in December 1999, when it had almost 30 years operation experience since the commencement of commercial operation in March 1970, many cracks were detected visually at the shroud support to reactor pressure vessel (RPV) weld metal (Ni-based alloy: Alloy 182) and confirmed with penetrant testing as well as by metallographic observation. Almost all cracks were found to propagate in the axial direction of the RPV ...
英字タイトル:
Evaluation on Crack Growth Analysis Model based on the Knowledge obtained from Stress Corrosion Cracking in Ni-based Alloy used for a Long Time in a BWR
英字タイトル:
Evaluation on Crack Growth Analysis Model based on the Knowledge obtained from Stress Corrosion Cracking in Ni-based Alloy used for a Long Time in a BWR
第13回
福島廃炉に向けた燃料取出しのための技術開発
著者:
木下 博文,Hirofumi KINOSHITA,吉田 拓真,Takuma YOSHIDA,清水 禎人,Sadato SHIMIZU,米谷 豊,Yutaka KOMETANI
発刊日:
公開日:
キーワードタグ:
decommissioning work fuel fuel debris high-dose radiation investigation rubble removal
木下 博文,Hirofumi KINOSHITA,吉田 拓真,Takuma YOSHIDA,清水 禎人,Sadato SHIMIZU,米谷 豊,Yutaka KOMETANI
発刊日:
公開日:
キーワードタグ:
decommissioning work fuel fuel debris high-dose radiation investigation rubble removal
The decommissioning work at Fukushima Daiichi Nuclear Power Station needs to plan based on the information of investigation in the reactor building and the environmental status such as radiation dose rate. It is necessary to develop the remote operation technologies for investigation in the reactor building, radiation measurement, removal of spent fuel and fuel debris. Hitachi Group is developing the various remote operation technologies for removal of spent fuels from the spent fuel pool and fuel debr...
英字タイトル:
Development of technology for fuel removal of the Fukushima Decommissioning
英字タイトル:
Development of technology for fuel removal of the Fukushima Decommissioning
論文
ＢＷＲ炉内構造物のニッケル基合金溶接部に発見された応力腐食割れの超音波探傷試験結果とその評価
著者:
青木 孝行,Takayuki AOKI,樋口 真一,Shinichi HIGUCHI,小林 広幸,Hiroyuki KOBAYASHI,清水 禎人,Sadato SHIMIZU
発刊日:
公開日:
キーワードタグ:
Boiling Water Reactor Ni-base Alloy Stress Corrosion Cracking TOFD Ultrasonic Examination
青木 孝行,Takayuki AOKI,樋口 真一,Shinichi HIGUCHI,小林 広幸,Hiroyuki KOBAYASHI,清水 禎人,Sadato SHIMIZU
発刊日:
公開日:
キーワードタグ:
Boiling Water Reactor Ni-base Alloy Stress Corrosion Cracking TOFD Ultrasonic Examination
A Ni-base alloy weld, including cracks due to stress corrosion cracking found in the reactor internal of the oldest BWR in Japan, Tsuruga unit 1, in 1999, was examined by three (3) types of UT method. After this examination, a depth of each crack was confirmed by carrying out a little excavation with a grinder and PT examination by turns until each crack disappeared. Then, the depth measured by the former method was compared with the one measured by the latter method. In this fashion, performances of...
英字タイトル:
Evaluation on Ultrasonic Examination Methods applied to Ni-base Alloy Weld including Cracks due to Stress Corrosion Cracking found in BWR Reactor Internal
英字タイトル:
Evaluation on Ultrasonic Examination Methods applied to Ni-base Alloy Weld including Cracks due to Stress Corrosion Cracking found in BWR Reactor Internal