Tooru OOTSUBO
著者に関連した記事は4件です。
更新情報
第5回
フェーズドアレイUTによる炉内配管への適用
著者:
平澤 泰治,Taiji HIRASAWA,湯口 康弘,Yasuhiro YUGUCHI,村上 功治,Koji MURAKAMI,大坪 徹,Tooru OOTSUBO,成瀬 克彦,Katsuhiko NARUSE
発刊日:
公開日:
キーワードタグ:
co Core spray piping Fatigue crack hirasawatoshiba jp Length and depth sizing E-mail Phased Array UT taiji
平澤 泰治,Taiji HIRASAWA,湯口 康弘,Yasuhiro YUGUCHI,村上 功治,Koji MURAKAMI,大坪 徹,Tooru OOTSUBO,成瀬 克彦,Katsuhiko NARUSE
発刊日:
公開日:
キーワードタグ:
co Core spray piping Fatigue crack hirasawatoshiba jp Length and depth sizing E-mail Phased Array UT taiji
The improvement of defect detection and sizing capabilities for nondestructive inspection technique has been required in order to ensure the reliable operation and life extension of nuclear power plant . Immersion phased array UT technique which is not affected the surface geometry of welds has been developed for inspection of BWR internals such as shroud, shroud support, and so on. Furthermore, thin -type array probe was developed and was examined in UT of core spray piping welds in the narrow region betw...
英字タイトル:
Application of Phased Array UT on BWR Reactor Internals Piping
英字タイトル:
Application of Phased Array UT on BWR Reactor Internals Piping
第7回
基調講演: EJAM New Technologyの活動状況
著者:
野本 敏治,Toshiharu NOMOTO,堂﨑 浩二,Koji DOZAKI,坂下 彰浩,Akihiro SAKASHITA,平野 伸明,Shinro HIRANO,大坪 徹,Tooru OOTSUBO,伊東 敬,Takashi ITO,宮口 仁一,Jinichi MIYAGUCHI,古村 一朗,Ichiro KOMURA,青木 孝行,Takayuki AOKI,中村 麻友,Mayu NAKAMURA,東原 奈美,Nami TOHARA
発刊日:
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EJAM Maintenance technology New Technology
野本 敏治,Toshiharu NOMOTO,堂﨑 浩二,Koji DOZAKI,坂下 彰浩,Akihiro SAKASHITA,平野 伸明,Shinro HIRANO,大坪 徹,Tooru OOTSUBO,伊東 敬,Takashi ITO,宮口 仁一,Jinichi MIYAGUCHI,古村 一朗,Ichiro KOMURA,青木 孝行,Takayuki AOKI,中村 麻友,Mayu NAKAMURA,東原 奈美,Nami TOHARA
発刊日:
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EJAM Maintenance technology New Technology
One year has passed since Electronic Journal of Advanced Maintenance (EJAM) was started on the website of Japan Society of M aintenology (ISM) May 25“, 2009. “New Technology' (NT) is one of the EJAM categories, and introduces widely advanced techniqu es developed or modified for maintenance. Twenty-two NT articles have been introduced on EJAM website so far as of May 25t“, 2010. This report describes the concept of NT, general features of NT articles, actual performance and future wishes for NT....
英字タイトル:
Current Status of EJAM ‘New Technology
英字タイトル:
Current Status of EJAM ‘New Technology
第2回
炉内点検技術と高経年化プラントへの適用
著者:
山本 智,Satoshi YAMAMOTO,平澤 泰治,Taiji HIRASAWA,大坪 徹,Tooru OOTSUBO,落合 誠,Makoto OCHIAI,坂口 正武,Masatake SAKAGUCHI,亀山 育子,Ikuko KAMEYAMA
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Laser-ultrasonic testing (Laser-UT) Phased array ultrasonic testing Reactor internals Remote operated vehicle (ROV) Stress corrosion cracking (SCC) Ultrasonic testing (UT)
山本 智,Satoshi YAMAMOTO,平澤 泰治,Taiji HIRASAWA,大坪 徹,Tooru OOTSUBO,落合 誠,Makoto OCHIAI,坂口 正武,Masatake SAKAGUCHI,亀山 育子,Ikuko KAMEYAMA
発刊日:
公開日:
キーワードタグ:
Laser-ultrasonic testing (Laser-UT) Phased array ultrasonic testing Reactor internals Remote operated vehicle (ROV) Stress corrosion cracking (SCC) Ultrasonic testing (UT)
The request of the inspection to reactor internals is increasing with application of the Japanese operation and maintenance code to aged nuclear power plants. Toshiba has developed many outstanding under water inspection t echnologies combined with ultrasonic testing (UT) techniques and remote operated vehicles (ROVs) technologies. Water gap phased array UT technique is capable to apply to all internals including complicated form part such a s reactor bottom head penetration weldment. Laser-ultrasonic te...
英字タイトル:
Inspection Technologies for Reactor Internals of Aged Nuclear Power Plants
英字タイトル:
Inspection Technologies for Reactor Internals of Aged Nuclear Power Plants
第6回
ＢＷＲの炉内構造物及び配管の保全技術
著者:
大坪 徹,Tooru OOTSUBO,伊東 敬,Takashi ITOU,坂下 彰浩,Akihiro SAKASHITA
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BWR EJAM PLR piping Preventive maintenance Reactor Internal Repair SCC
大坪 徹,Tooru OOTSUBO,伊東 敬,Takashi ITOU,坂下 彰浩,Akihiro SAKASHITA
発刊日:
公開日:
キーワードタグ:
BWR EJAM PLR piping Preventive maintenance Reactor Internal Repair SCC
Stress corrosion cracking of welding portion has found in many domestic and foreign BWR reactor internals and Primary Loop Recirculation piping. Also, repair and preventive maintenance technologies for SCC has been developed and/or adopted to BWRs in recent years. This paper introduces the sample of these technologies, such as seal-welding fo r SCC on BWR reactor internals, preventive maintenance technology for PLR piping such as Corrosion Resistant Cladding, Internal Polishing and Induction Heating Stress...
英字タイトル:
Repair and Preventive maintenance Technology for BWR Reactor Internals and Piping
英字タイトル:
Repair and Preventive maintenance Technology for BWR Reactor Internals and Piping