第5回
中性子照射によって延性が著しく低下する場合の延性破壊条件と構造健全性確保の概念
著者:
實川 資朗,Shiro JITSUKAWA,鈴木 一彦,Kazuhiko SUZUKI,大久保 成彰,Nariaki OKUBO,芝 清之,Kiyoyuki SHIBA,高田 文樹,Fumiki TAKADA,近江 正男,Masao OHMI,中川 哲也,Tetsuya NAKAGAWA
発刊日:
公開日:
キーワードタグ:
Results of irradiation experiment on the degradation of ductility of 8-9Cr reduced activation ferritic/martensitic steels are introduced, including those of irradiated austenitic steels. M acroscopic models of post irradiation tensile and fatigue properties obtained from the results are shown. Concept of the models should be essential for future design criteria development....
英字タイトル:
Ductility loss of materials by neutron irradiation and structural integrity of reactor core
第11回
東海再処理施設における分析設備の保守
著者:
鈴木 久規,Hisanori SUZUKI,永山 哲也,Tetsuya NAGAYAMA,堀籠 和志,Kazushi HORIGOME,石橋 篤,Atsushi ISHIBASHI,北尾 貴彦,Tahiko KITAO,駿河谷 直樹,Naoki SURUGAYA
発刊日:
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キーワードタグ:
The Tokai Reprocessing Plant (TRP) is developing the technology to recover uranium and plutonium from spent nuclear fuel. There is an analytical laboratory which was built in 1977, as one of the most important facilities for process and material control analyses at the TRP. Samples taken from each process are a nalyzed by various analytical methods using hot cells, glove boxes and hume-hoods. A large number of maintenance work have been so far carried out and diffe rent types of experience have been accum...
英字タイトル:
Maintenance experiences at analytical laboratory at the Tokai Reprocessing Plant
第17回
核燃料物質使用施設の高経年化リスク評価手法の開発 (1)リスク評価フローの検討
著者:
玉置 裕一,磯﨑 涼佑,鈴木 隆太,赤田 雅貴,澤幡 哲司, 米澤 諒真,鈴木 尚,坂本 直樹,水越 保貴,(JAEA)
発刊日:
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The five post-irradiation examination facilities in the Oarai Research and Development Institute of the Japan Atomic Energy Agency have been operated for over 40 years in order to investigate the irradiation performance and physicochemical characteristics of nuclear fuels and materials for fast reactors. The equipments associated with these facilities have been managed to maintain secure from the problems that occurred in the process of aging. Therefore, we established a safety assessment method for aging f...
英字タイトル:
Development of risk assessment method to cope with an aging degradation for the facilities using nuclear material. (1) Risk assessment flow of equipments
第5回
核融合実験炉ITER用ダイバータ受熱機器における非破壊検査技術の開発
著者:
江里 幸一郎,Koichiro EZATO,鈴木 哲,Satoshi SUZUKI,大楽 正幸,Masayuki DAIRAKU,横山 堅二,Kenji YOKOYAMA,秋場 真人,Masato AKIBA
発刊日:
公開日:
キーワードタグ:
Non-destructive examination (NDE) methods for joint interfaces between different materials in high heat flux components of ITER divertor should be urgently developed to assure qualit y and reliability of joining techniques. This paper reports the present R&Ds status of NDE for ITER divertor and its outlook. The detection ability of joint defect by using ultrasonic wave and thermography NDE are examined in the joint interface between armor tiles and a cooling tubes of divertor mock-ups. The results of both ...
英字タイトル:
Development of Non-destructive technique for ITER divertor high heat flux component
第13回
福島第一原子力発電所使用済燃料プール貯蔵燃料及び燃料デブリ取出しに向けた取り組み
著者:
東倉 一郎,Ichiro TOKURA,篠崎 史人,Fumihito SHINOZAKI,鈴木 淳,Jun SUZUKI,浦西 敦義,Atsuyoshi URANISHI,大和 正樹,Masaki YAMATO,宮本 哲昌,Akimasa MIYAMOTO
発刊日:
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Toshiba and TEPCO completed the removal of large debris from the spent fuel pool (SFP) in November 2015. The large debris had been an obstacle to start the fuel debris removal work and had been necessary to be removed quickly in terms of risk reduction. Continuously, Toshiba and TEPCO are preparing for removal of small debris and spent fuels. Also, Toshiba and IRID are investigating of PCV interior and working in research and development to determine construction methods considering amount, location an...
英字タイトル:
Effort aimed at removal of stored fuels from SFP and fuel debris inside PCV in Fukushima Daiichi Nuclear Power Station
第5回
赤外熱画像を用いた核融合実験炉ダイバータ用非破壊検査装置の開発
著者:
横山 堅二,Kenji YOKOYAMA,鈴木 哲,Satoshi SUZUKI,江里 幸一郎,Kouichiro EZATO,関 洋治,Yohji SEKI,榎枝 幹夫,Mikio ENOEDA,秋場 真人,Masato AKIBA
発刊日:
公開日:
キーワードタグ:
An infrared thermography NDE facility which is utilized in the acceptance test of ITER d ivertor components has been developed in JAEA. This NDE facility can inspect the integri ty of the bonding interface of the divertor components based on its surface temperature response by means of switching of hot (95 deg C)/cold (5 deg C) water. The advantages of this facility are 1) to have active coolant purging system which enables rapid temperatu re change and 2) to inspect the surface and the both side walls of...
英字タイトル:
Development of a non destructive evaluation system using infrared images for divertor on nuclearfusion experiment reactor
第3回
軽水炉圧力容器鋼溶接部の照射脆化評価技術
著者:
熊野 秀樹,Hideki YUYA,鈴木 哲也,Tetsuya SUZUKI,肥田 茂,Shigeru HIDA,木村 晃彦,Akihiko KIMURA
発刊日:
公開日:
キーワードタグ:
The ductile-brittle transition behavior of neutron-irradiated welded A533B Cl.1 steel has been studied by means of small specimen test technique for discussing the specime n size effects on the impact properties. Standard size, one-third size and 1.5mm size Charpy V-notch specimens were prepared. Neutron irradiation was performed in JMTR wit h fluencies up to 0.75 and 1.3 X 1024 n/m°(E>1 MeV). Normalization of the USE is done by a curve fitting method and the USE of different size of specimens can be expre...
英字タイトル:
Evaluation Technique of Neutron-Irradiation Embrittlement in Welded RPV
第14回
電磁超音波を用いた減肉モニタリングシステムの 福島第一原子力発電所4号機使用済燃料プール冷却配管への適用
著者:
高木 敏行,Toshiyuki TAKAGI,内一 哲哉,Tetsuya UCHIMOTO,浦山 良一,Ryoichi URAYAMA,鈴木 聡則,Akinori SUZUKI
発刊日:
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キーワードタグ:
In the decommissioning measures of Fukushima Daiichi Nuclear Power plant (1F), it is important to ensure the thermal stability of the reactor and the whole system by the cooling system in order to prevent criticality of fuel and fuel debris. However, wall thinning is concerned due to the corrosion in the piping of the cooling system. In order to maintain the safety of the system, it is necessary to manage the piping thinning. In this study, the EMAT thickness monitoring system, which can measure thickne...
英字タイトル:
Application of monitoring system using electromagnetic acoustic transducers for wall thickness measurement to Fukushima Daiichi nuclear power plant Unit 4 spent fuel pool cooling piping
第3回
電磁超音波・渦電流複合センサの開発とその有効性の検証
著者:
鈴木 研一郎,Kenichiro SUZUKI,内一 哲哉,Tetsuya UCHIMOTO,高木 敏行,Toshiyuki TAKAGI,佐藤 武志,Takeshi SATO,Philippe Guy,Amelie Casse
発刊日:
公開日:
キーワードタグ:
In this study, we propose a novel EMAT-ECT multi sensor aiming at advanced structural health monitoring. For the purpose, proto-type EMAT-ECT multi-sensor was developed and their functions both as ECT and EMAT prove were evaluated. Experimental results of pulse ECT using the EMAT-ECT multi-sensor showed that the pr oposed sensor has a capability of detection and sizing of flaws. Experimental results of EMAT evaluation using the EMAT-ECT multi-sensor showed that ultrasoni c wave was transmitted by EMAT-ECT ...
英字タイトル:
Development of novel EMAT-ECT multi-sensor and verification of its feasibility
第6回
5本ノズル型ジェットポンプの性能回復に関する研究
著者:
熊野 秀樹,Hideki YUYA,原 哲哉,Tetsuya HARA,鈴木 純也,Junya SUZUKI,伊藤 圭介,Keisuke ITOU,鍵谷 幸生,Yukio KAGIYA,社河内 敏彦,Toshihiko SHAKOUCHI
発刊日:
公開日:
キーワードタグ:
The degradation of 1-nozzle type Jet Pump (JP) efficiency by crud deposition has been recognized in some BWRs. In order to remove crud, we must clean each o r all of JP inner surface. The increase in cleaning surface area induces the increase in outage period and cost, therefore, in the previous study we looked for the most effective cleaning portion at inner surface for efficiency recovery. In this study, for the 5-nozzle type JP, we evaluated the effect of crud portion on decrease in efficiency of 5-noz...
英字タイトル:
Studies on Recovering Method of 5-nozzle type Jet Pump Efficiency