太田 隆
著者に関連した記事は3件です。
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論文
ステンレス鋼溶接金属を透過したUT(検出)確認試験研究の成果
著者:
永田 義昭,Yoshiaki NAGATA,長谷川 勝広,Katsuhiro HASEGAWA,久米田 正邦,Masakuni KUMEDA,稲垣 哲彦,Tetsuhiko INAGAKI,中田 親秀,Chikahide NAKADA,太田 隆,Takashi OHTA,田口 豊信,Toyonobu TAGUCHI,米谷 豊,Yutaka KOMETANI,清水 康,Yasushi SHIMIZU,三橋 忠浩,Tadahiro MITSUHASHI,東海林 一,Hajime SHOHJI,山口 篤憲,Atsunori YAMAGUCHI,杉林 卓也,Takuya SUGIBAYASHI,小林 輝男,Teruo KOBAYASHI
発刊日:
公開日:
キーワードタグ:
Phased array UT Stainless steel Stress Corrosion Cracking Ultrasonic Testing
永田 義昭,Yoshiaki NAGATA,長谷川 勝広,Katsuhiro HASEGAWA,久米田 正邦,Masakuni KUMEDA,稲垣 哲彦,Tetsuhiko INAGAKI,中田 親秀,Chikahide NAKADA,太田 隆,Takashi OHTA,田口 豊信,Toyonobu TAGUCHI,米谷 豊,Yutaka KOMETANI,清水 康,Yasushi SHIMIZU,三橋 忠浩,Tadahiro MITSUHASHI,東海林 一,Hajime SHOHJI,山口 篤憲,Atsunori YAMAGUCHI,杉林 卓也,Takuya SUGIBAYASHI,小林 輝男,Teruo KOBAYASHI
発刊日:
公開日:
キーワードタグ:
Phased array UT Stainless steel Stress Corrosion Cracking Ultrasonic Testing
BWR owners and plant fabricators have been making efforts to decrease the ISI parts where UT is difficult to be conducted. For that purpose, UT verification test for both detection and sizing qualification through deposit of pipe weld joint started in 2009 and will last until 2011. In 2009, UT verification test for stainless steel pipe weld joint has been performed. Test samples are stainless steel pipes with welds and sizes are 600A.350A.150A with EDM notches and/or SCC cracks. Angle beam methods and...
英字タイトル:
Result of UT verification test for Stainless Steel through weld deposit
英字タイトル:
Result of UT verification test for Stainless Steel through weld deposit
第7回
ステンレス鋼溶接金属を透過したＵＴ(検出)確認試験研究の成果
著者:
永田 義昭,Yoshiaki NAGATA,長谷川 勝広,Katsuhiro HASEGAWA,久米田 正邦,Masakuni KUMEDA,稲垣 哲彦,Tetsuhiko INAGAKI,中田 親秀,Chikahide NAKADA,太田 隆,Takashi OHTA,田口 豊,Yutaka TAGUCHI,米谷 豊,Yutaka KOMETANI,清水 康,Yasushi SHIMIZU,三橋 忠浩,Tadahiro MITSUHASHI,東海林 一,Hajime SHOHJI,山口 篤憲,Atsunori YAMAGUCHI,杉林 卓也,Takuya SUGIBAYASHI,小林 輝男,Teruo KOBAYASHI
発刊日:
公開日:
キーワードタグ:
Phased array UT Stainless steel Stress Corrosion Cracking Ultrasonic Testing
永田 義昭,Yoshiaki NAGATA,長谷川 勝広,Katsuhiro HASEGAWA,久米田 正邦,Masakuni KUMEDA,稲垣 哲彦,Tetsuhiko INAGAKI,中田 親秀,Chikahide NAKADA,太田 隆,Takashi OHTA,田口 豊,Yutaka TAGUCHI,米谷 豊,Yutaka KOMETANI,清水 康,Yasushi SHIMIZU,三橋 忠浩,Tadahiro MITSUHASHI,東海林 一,Hajime SHOHJI,山口 篤憲,Atsunori YAMAGUCHI,杉林 卓也,Takuya SUGIBAYASHI,小林 輝男,Teruo KOBAYASHI
発刊日:
公開日:
キーワードタグ:
Phased array UT Stainless steel Stress Corrosion Cracking Ultrasonic Testing
BWR owners and plant fabricators have been making efforts to decrease the ISI parts where UT is difficult to be cond ucted. For that purpose, UT verification test for both detection and sizing qualification through deposit of pipe wel d joint started in 2009 and will last until 2011. In 2009, UT verification test for stainless steel pipe weld joint has been performed. Test samples are stainless steel pipes with welds and sizes are 600A.350A.150A with EDM notches a nd/or SCCs. Angle beam methods and phased...
英字タイトル:
Result of UT verification test for Stainless Steel through weld deposit
英字タイトル:
Result of UT verification test for Stainless Steel through weld deposit
第5回
高温ガス炉の保全技術の開発
著者:
古澤 孝之,本間 史隆,猪井 宏幸,澤畑 洋明,根本 隆弘,渡辺 周二,太田 幸丸
発刊日:
公開日:
キーワードタグ:
Gas turbine High temperature component HTGR HTTR Inspection method Preservation philosophy Preservation technology Reserved shutdown system
古澤 孝之,本間 史隆,猪井 宏幸,澤畑 洋明,根本 隆弘,渡辺 周二,太田 幸丸
発刊日:
公開日:
キーワードタグ:
Gas turbine High temperature component HTGR HTTR Inspection method Preservation philosophy Preservation technology Reserved shutdown system
Japan Atomic Energy Agency has constructed the HTTR (High Temperature engineering Test Reactor), which is the Japa n's first High Temperature Gas-cooled Reactor (HTGR). The HTTR achieved the full power of 30MW and reactor outlet coolant temperature of 950°C on April 19, 2004. Based on the HTTR maintenance experiences, the preservation techno logy for HTGR are developed. This paper describes its preservation philosophy and typical developed technologies....
英字タイトル:
Development of preservation technology for High Temperature Gas-cooled Reactor
英字タイトル:
Development of preservation technology for High Temperature Gas-cooled Reactor