第3回
もんじゅ」原子炉容器 ISI システムの開発
著者:
田川 明広,Akihiro TAGAWA,岡本 久彦,Hisahiko OKAMOTO,上田 雅司,Masashi UEDA,山下 卓哉,Takuya YAMASHITA
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This paper describes the development of a new inspection robot and support system used for the in-service inspection (ISI) of the reactor vessel of the FBR MONJU. The inspection is carried o ut using a CCD camera for visual tests and an EMAT for volumetric tests at elevated temperature (200 degree C) and high irradiation dose condition (10Sv/hr). The applicability of a commercia l CCD camera and an EMAT have been confirmed by experiments under severe conditions. In addition, reduction of the robot weight f...
英字タイトル:
Development of ISI system for FBR MONJU reactor vessel
第5回
ハイブリット計測による配管ヘルスモニタリング法
著者:
田川 明広,Akihiro TAGAWA,上田 雅司,Masashi UEDA,宮原 信哉,Shinya MIYAHARA,山下 卓哉,Takuya YAMASHITA
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This paper describes the development of a new sensor for the pipe health monitoring. The Hyb rid measuring using EMAT was made as a trial. It examined and checked that it could measure....
英字タイトル:
The pipe health monitoring method by Hybrid measurement using ultrasonic
論文
ハイブリッド計測による配管ヘルスモニタリング法の研究
著者:
田川 明広,Akihiro TAGAWA,小島 史男,Fumio KOJIMA
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The purpose of this study is to develop a hybrid sensor to be able to measure two or more physical values (the pipe surface temperature, the pipe wall thinning and the temperature of an internal fluid) with one sensor with an electromagnetic acoustic transducer. Each result of a measurement can improve the measurement precision by doing working that calibrate each other. The piping surface temperature was measured by converting the direct current resistance at the temperature by using the EMAT coil. A...
英字タイトル:
Study on pipe health monitoring method by hybrid measurement using electromagnetic ultrasonic
第5回
伝熱管内壁検査補修技術開発の概要
著者:
西村 昭彦,Akihiko NISHIMURA,岡 潔,Kiyoshi OKA,山口 智彦,Toshihiko YAMAGUCHI,山下 卓哉,Takuya YAMASHITA,田川 明広,Akihiro TAGAWA,ミハラケ オビデウ,Ovidiu MIHALACHE,島田 幸洋,Ukihiro SHIMADA
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A hybrid optical fiber scope and a laser processing head were combined with an eddy current testing un it for the inspection and repairing for Fast Breeder Reactor's heat exchanger pipes. The project propo ses an effective cost reduction method for maintenance of FBR by extension of the heat exchanger's lif etime. By the end of March 2010, a prototype probing system for heat exchanger pipes will be completed....
英字タイトル:
Development of Inspection and Repairing Technology for FBR Heat Exchanger Pipes
第6回
伝熱管内壁検査補修技術開発(その2)ソフトウエア開発と性能試験準備
著者:
西村 昭彦,Akihiko NISHIMURA,岡 潔,Kiyoshi OKA,山口 智彦,Toshihiko YAMAGUCHI,赤津 朋宏,Tomohiro AKATSU,関 健史,Takeshi SEKI,ミハラケ オビデウ,Ovidiu MIHALACHE,島田 幸洋,Yukihiro SHIMADA,田川 明広,Akihiro TAGAWA,山下 卓哉,Takuya YAMASHITA
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In order to maintain FBR heat exchanger tubes, a new probe system was designed. A coupling u nit and operational software are key components in the second year. The coupling unit to com bine a high energy laser beam and optical fiberscope images was developed. The operational s oftware successfully controlled an eddy current testing device and a laser processing head....
英字タイトル:
Development of Inspection and Repairing Technology for FBR Heat Exchanger tubes (II)Preparation of Operation Software and Performance Check
第10回
帰還困難区域における路面除染の予測と実証
著者:
田川 明広,Akihiro TAGAWA,山下 卓哉,Takuya YAMASHITA
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This paper compared evaluation results of decontamination simulation with the actual decontamination result. One of the major factors that decontamination does not proceed, is that the decontamination results are unpredictable. JAEA has developed the software that can be predictive simulation of decontamination with a simple user interface. The purpose of this study is that to evaluate the simulation accuracy. JAEA evaluated accuracies that compared simulation results of decontamination simulation with...
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Decontamination estimate and demonstration test results on road in the return difficult area.
第6回
減肉モニタリング用EMAT の高温耐久試験結果
著者:
田川 明広,Akihiro TAGAWA,藤木 一成,Kazunari FUJIKI
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This study checks the high-temperature durability of the electromagnetic acoustic transducer (EMAT) for pipe wall inning. We inserted EMAT into the oven and measured the 10mm thickness specimen by EMAT about two years. Measurement was carried out by two kinds, a pulse echo method and a pulse echo resonance method. And igh-temperature durability was checked by both of the measuring methods. Compared with the pulse echo method, the ulse echo resonance method of measurement accuracy was better. The filter pro...
英字タイトル:
The durability test result in high temperature of EMAT for pipe wall thinning monitoring
論文
研究開発段階発電用原子炉の特徴を考慮した 保守管理の提案
著者:
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
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A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. Finally, an example that the proposal was applied to setting maintenance program of sodium-cooled fast reactor was presented. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features
第13回
研究開発段階発電用原子炉の特徴を考慮した 保守管理の提案 (1)基本要件
著者:
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
発刊日:
公開日:
キーワードタグ:
A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (1) Basic Requirements
第13回
研究開発段階発電用原子炉の特徴を考慮した 保守管理の提案 (2)適用事例
著者:
近澤 佳隆,Yoshitaka CHIKAZAWA,髙屋 茂,Shigeru TAKAYA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
発刊日:
公開日:
キーワードタグ:
A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage were first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. In this paper, requirements on maintenance program of NPP at R&D stage were clarified and an example that the proposal was applie...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (2) case study