椿 正昭
著者に関連した記事は3件です。
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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）
発刊日:
公開日:
キーワードタグ:
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）
発刊日:
公開日:
キーワードタグ:
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
論文
実機プラントの炉心シュラウドへのウォータージェットピーニング（WJP）適用とWJP施工後の残留応力測定
著者:
大城戸 忍,Shinobu OKIDO,椿 正昭,Masaaki TSUBAKI,千葉 篤志,Atsushi CHIBA,佐川 渉,Wataru SAGAWA,松田 徹,Toru MATSUDA
発刊日:
公開日:
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Nuclear Power Plant Reactor Internal Components Residual Stress Shroud Water Jet Peening(WJP) Weld X-ray Stress Measurement
大城戸 忍,Shinobu OKIDO,椿 正昭,Masaaki TSUBAKI,千葉 篤志,Atsushi CHIBA,佐川 渉,Wataru SAGAWA,松田 徹,Toru MATSUDA
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公開日:
キーワードタグ:
Nuclear Power Plant Reactor Internal Components Residual Stress Shroud Water Jet Peening(WJP) Weld X-ray Stress Measurement
Residual stress improvement technologies have been developed and applied to Boiling Water Reactor (BWR) plant components in order to prevent from stress corrosion cracking (SCC) of stainless steel and Ni-based alloy materials. Water Jet Peening (WJP) is one of the effective procedures for residual stress improvement, and has the various advantages for the application to the reactor internal components of the operating nuclear power plants because WJP uses only water for residual stress improvement. As...
英字タイトル:
Application of Water Jet Peening to the Shroud Components in BWR Power Plant and Residual Stress Measurement after WJP.
英字タイトル:
Application of Water Jet Peening to the Shroud Components in BWR Power Plant and Residual Stress Measurement after WJP.
第6回
沸騰水型原子炉の蒸気乾燥器及び主蒸気系の流力音響共鳴振動
著者:
高橋 志郎,Shiro TAKAHASHI,奥山 圭太,Keita OKUYAMA,田村 明紀,Akinori TAMURA,大塚 雅哉,Masaya OHTSUKA,吉川 和宏,Kazuhiro YOSHIKAWA,椿 正昭,Masaaki TSUBAKI,馬渕 靖宏,Yasuhiro MABUCHI
発刊日:
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Boiling Water Reactor Flow-Induced Acoustic Resonance Safety Relief Valve Steam Dryer
高橋 志郎,Shiro TAKAHASHI,奥山 圭太,Keita OKUYAMA,田村 明紀,Akinori TAMURA,大塚 雅哉,Masaya OHTSUKA,吉川 和宏,Kazuhiro YOSHIKAWA,椿 正昭,Masaaki TSUBAKI,馬渕 靖宏,Yasuhiro MABUCHI
発刊日:
公開日:
キーワードタグ:
Boiling Water Reactor Flow-Induced Acoustic Resonance Safety Relief Valve Steam Dryer
The BWR-3 steam dryer in the Quad Cities Unit 2 Nuclear Power Plant was damaged by high cycle fatigue due to acoustic-induced vibration under extended power up-rate conditions. The dryer failure was as attributed to flow-in duced acoustic resonance at the stub pipes of safety relief valves (SRVs) in the main steam lines (MSLs). The acoustic resonance was considered to be generated by interaction between the sound field and unstable shear layer s across the closed side branches with SRV stub pipes. We have ...
英字タイトル:
Flow-induced Acoustic Resonance Vibration of Main Steam Lines and Dryer in Boiling Water Reactor
英字タイトル:
Flow-induced Acoustic Resonance Vibration of Main Steam Lines and Dryer in Boiling Water Reactor