沖村 浩司
著者に関連した記事は6件です。
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第6回
加圧水型原子力発電プラントに対する保全（応力腐食割れ対策）
著者:
佐藤 知伸,Tomonobu SATO,岡部 武利,Taketoshi OKABE,沖村 浩司,Koji OKIMURA,豊田 真彦,Masahiko TOYODA,前口 貴治,Takaharu MAEGUCHI
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PWR PWSCC RV SG shot penning USP water jet penning WJP
佐藤 知伸,Tomonobu SATO,岡部 武利,Taketoshi OKABE,沖村 浩司,Koji OKIMURA,豊田 真彦,Masahiko TOYODA,前口 貴治,Takaharu MAEGUCHI
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PWR PWSCC RV SG shot penning USP water jet penning WJP
As a countermeasure against SCC (stress corrosion cracking), MHI (Mitsubish i Heavy Industries, Ltd.) have developed some residual stress improvement m ethods, as Water Jet Peening (WJP) for components under water condition, a nd Shot Peening by Ultrasonic-wave vibration (USP) for components under air condition. The SCC occurred in high nickel based metal and welding material in pressurized water reactor (PWR) plants has become to be conspicuous iss ue in both Japan and abroad. In this paper, validity of s...
英字タイトル:
Maintenance Technologies for Degradation of Pressurized Water Reactor Power Plants
英字タイトル:
Maintenance Technologies for Degradation of Pressurized Water Reactor Power Plants
論文
原子力発電所における新保全技術としてのテンパービード工法の開発・適用
著者:
平野 伸朗,Shinro HIRANO,瀬良 健彦,Takehiko SERA,千種 直樹,Naoki CHIGUSA,沖村 浩司,Koji OKIMURA,西本 和俊,Kazutoshi NISHIMOTO
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Ambient temper bead welding No action letter Nuclear Power Plants Qualification RNP
平野 伸朗,Shinro HIRANO,瀬良 健彦,Takehiko SERA,千種 直樹,Naoki CHIGUSA,沖村 浩司,Koji OKIMURA,西本 和俊,Kazutoshi NISHIMOTO
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Ambient temper bead welding No action letter Nuclear Power Plants Qualification RNP
Japanese government has recently addressed a policy to increase capacity factor of existing nuclear PPs to achieve the goal to decrease the emission of CO2. Numerous preventive measures have taken in nuclear power plants to minimize the risk of unexpected long shutdown. Newly developed mitigation measures or repair methods need to be qualified to satisfy regulatory standards, before it is implemented to nuclear power plants. The qualification process needs to comply regulatory standards though it may consum...
英字タイトル:
R/D and implement of temper bead welding as newly developed maintenance technique in nuclear power plant
英字タイトル:
R/D and implement of temper bead welding as newly developed maintenance technique in nuclear power plant
第6回
原子炉容器上蓋貫通部のPWSCC 対策のための気中封止溶接工法
著者:
沖村 浩司,Koji OKIMURA,宮口 仁一,Jinichi MIYAGUCHI
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Alloy 690 GTA welding J-weld of penetration nozzle PWSCC Reactor vessel head Seal welding
沖村 浩司,Koji OKIMURA,宮口 仁一,Jinichi MIYAGUCHI
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Alloy 690 GTA welding J-weld of penetration nozzle PWSCC Reactor vessel head Seal welding
The penetration nozzles of reactor vessel head, which are made of alloy 600, have sensitivity to Stress Corrosi Cracking in PWR primar y water environment (PWSCC). To preparing the countermeasure in case of cracks oh during the inspection activity, a dedicated seal wel ding method has been developed, where alloy 690 is used fd metal to isolate the cracking from the environment. This method was applie d to an actual plant effectively, wh leakage at the penetration due to...
英字タイトル:
Seal Welding of PWSCC at J-weld of Reactor Vessel Head Penetration Nozzle
英字タイトル:
Seal Welding of PWSCC at J-weld of Reactor Vessel Head Penetration Nozzle
第9回
国内PWRプラントへの超音波ショットピーニング技術適用
著者:
山本 剛,Yamamoto TAKESHI,濱本 智元,Hamamoto TOMOCHIKA,沖村 浩司,Okimura KOJI
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steam generator nozzle stress corrosion cracks ultrasonic shot peening
山本 剛,Yamamoto TAKESHI,濱本 智元,Hamamoto TOMOCHIKA,沖村 浩司,Okimura KOJI
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steam generator nozzle stress corrosion cracks ultrasonic shot peening
An effective countermeasure against stress corrosion cracks in nozzle welds is to improve the surface residual stress. A new tec hnique of the ultrasonic shot peening (USP) for steam generator (SG) nozzles will be introduced as a method to improve the residu al stress on Alloy 600 Welds. This method changes the compressive stress by applying plastic strain to the surface via the impac t force of the shot material during the shot peening. We have successfully performed 14 USP operations in actual plants in ...
英字タイトル:
Application of Ultrasonic Shot Peening To Steam Generator Nozzles
英字タイトル:
Application of Ultrasonic Shot Peening To Steam Generator Nozzles
第15回
国内初のPWR廃止措置系統除染工事について
著者:
新田 義一,沖村 浩司,上田 剛史,鬼塚 博徳,上野 怜子,（三菱重工） 宮井 勲,藤田 隆之,野村 厚夫,（原子力サービスエンジニアリング）
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Decommissioning DF FSD Mihama Unit 1 & 2 Nickel alloy 690 PWR
新田 義一,沖村 浩司,上田 剛史,鬼塚 博徳,上野 怜子,（三菱重工） 宮井 勲,藤田 隆之,野村 厚夫,（原子力サービスエンジニアリング）
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Decommissioning DF FSD Mihama Unit 1 & 2 Nickel alloy 690 PWR
Mihama Unit 1 & 2 are the first decommissioned nuclear power plants in the Japanese PWR (Pressurized Water Reactor). FSD (Full System Decontamination) in PWR has never been conducted in Japan before. FSD in Mihama Unit 1 & 2 is the first one in the Japanese PWR. On the other hand, heat transfer tubes of steam generator are made of nickel alloy 690. Chemical decontamination for nickel alloy 690 has never been conducted in the world. As the result, the target which DF (decontamination factor) is over 30 is ac...
英字タイトル:
The nation’s first FSD for PWR decommissioning
英字タイトル:
The nation’s first FSD for PWR decommissioning
第17回
日本保全学会の保全遺産 原子力発電所のピーニングによる 応力腐食割れ抑制技術
著者:
今野 隆博,（日立GE）,石橋 文彦,（東芝ESS）,沖村 浩司,（三菱重工）
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Maintenance Heritage Peening Technology SCC Stress Corrosion Cracking
今野 隆博,（日立GE）,石橋 文彦,（東芝ESS）,沖村 浩司,（三菱重工）
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Maintenance Heritage Peening Technology SCC Stress Corrosion Cracking
The SCC Protect Technology by Peening is registered in The Maintenance Heritage by JSM We introduce The SCC Protect Technology by Peening in NPS...
英字タイトル:
The SCC Protect Technology by Peening in NPS
英字タイトル:
The SCC Protect Technology by Peening in NPS