127件が見つかりました。

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第14回
浜岡原子力発電所の安全対策について~今、総力を結集して~(動画紹介)
著者:
鈴木 直浩,Naohiro SUZUKI
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The Hamaoka Nuclear Power Station has always embraced the most up-to-date knowledge in its effort to enhance safety. We have been carrying out safety measures both before and after the accident at TEPCO's Fukushima Daiichi Nuclear Power Station, including countermeasures for tsunami and severe accidents. In response to the government introduction of New Regulatory Requirements, we are adopting a series of safety measures. No More Fukushima Daiichi Accidents With this resolve, the Hamaoka Nuclear Power Sta...
英字タイトル:
Safety enhancement measures at the Hamaoka Nuclear Power Station
第14回
海外における電気品の EQ(Environmental Qualification) に関する動向
著者:
中村 理恵,Rie NAKAMURA
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Demonstration that the electric equipment important to safety can perform the required function in harsh environment during/after design bases accident by the end of life is called _Environmental Qualification”. EQ is regulatory requirement and licensing bases in the US and many countries. In the US regulation, it is required to develop EQ program, EQ component list and to maintain EQ data and records. Also the US NRC has started the EQ program inspection as a first design bases assurance inspection from...
英字タイトル:
Status on Environmental Qualification of Electrical Component in Foreign Country
第14回
渦電流磁気指紋法による炭素鋼の残留ひずみ評価
著者:
松本 貴則,Takanori MATSUMOTO,内一 哲哉,Tetsuya UCHIMOTO,高木 敏行,Toshiyuki TAKAGI,阿部 悟,Satoru ABE,熊野 秀樹,Hideki YUYA
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This study aims at proposing a novel magnetic testing method, eddy current magnetic signature method for evaluation of residual strain in carbon steels. This method characterize the eddy current magnetic signatures that is eddy current signals in an impedance plain during magnetization process. In order to discuss the feasibility of this method, eddy current magnetic signatures of a set of tensile test specimens are investigated. The relationship between eddy current signature and plastic deformation is di...
英字タイトル:
Nondestructive Evaluation of Residual Strain in Carbon Steels by Eddy Current Magnetic Signature Method
第14回
炉内構造物等点検評価ガイドラインの整備について
著者:
関 弘明,Hiroaki SEKI,小林 広幸,Hiroyuki KOBAYASHI,中野 守人,Morihito NAKANO,村井 荘太郎,Soutarou MURAI
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The guideline committee for the inspection and evaluation of Reactor Vessel Internals of JANSI (Japan Nuclear Safety Institute) has been developing many guidelines based on principle which the conservative methodology, and covered both individual inspection method of reactor internals and application of repair methods for reactor internals. In this paper, some aspects of the JANSI-VIP-21 (Guidelines for the inspection and evaluation of Reactor Vessel Internals, revised Mar.2017) which is summary document o...
英字タイトル:
Outlines of Guidelines for the Inspection and Evaluation of Reactor Vessel Internals
第14回
炉内計装筒管台溶接部およびその補修溶接時を 想定した残留応力解析
著者:
望月 正人,Masahito MOCHIZUKI,岡野 成威,Shigetaka OKANO,柏山 忠義,Tadayoshi KASHIYAMA,丹羽 悠介,Yusuke NIWA,亀山 雅司,Masashi KAMEYAMA,中野 守人,Morihito NAKANO
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In this study, a fast simulation technique of Iterative Substructure Method (ISM) was applied for numerical analysis of the distribution of residual stress by J-weld and repair weld of Bottom Mounted Instrument (BMI) nozzle in reactor vessel penetration. The calculated results were compared with the measured values to validate the constructed residual stress analysis model. The effect of BMI mounting angles on distribution of residual stress at J-welds was investigated. Based on the results, similarity and...
英字タイトル:
Numerical Analysis of Residual Stress by J-weld and Repair Weld of Bottom Mounted Instrument Nozzles in Reactor Vessel Penetration
第14回
炭素鋼の流動下腐食挙動と律速過程の評価
著者:
阿部 博志,Hiroshi ABE,佐藤 祥平,Shohei SATO
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In order to proceed the decommissioning of the FuNushima Daiichi Nuclear Power Plant safely, it is important to maintain integrity of cooling system for fuel debris and spent fuels. Most part of the piping systems are made of carbon steel. This study has been done to understand rate-determining processes of carbon steel corrosion under current and future FuNushima Daiichi NPP conditions as functions of flow conditions and dissolved oxygen level by using electrochemical tests with rotating cylindrical ...
英字タイトル:
Corrosion behavior of carbon steels under flow and its rate-determining processes 渡邉 豊 YutaNa WATANABE Member
第14回
状態基準保全移行に向けた取り組み
著者:
佐藤 優樹,Yuki SATO
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At Oangawa Nuclear Power Station, the maintenance for the plant equipment has been performed by TBM which is based on the operation period of the equipment, and by BDM which is to be repaired the equipment by each break down. However, since FY2007, we have introduced CM to the plant equipment diagnosis for part of equipment, and performed TBM + CM maintenance. From this fiscal year, we evaluated those equipment started CBM performing for those representative TBM + CM to equipment. apply CBM which is ba...
英字タイトル:
Action for the Condition Based Maintenance shift
第14回
発電プラント内の無線ネットワーク構築に向けた RC 壁透過波の利用可能性に関する検討
著者:
佐藤 義人,Yoshihito SATO,山田 勉,Tsutomu YAMADA,里見 弘久,Hirohisa SATOMI,大場 希美,Nozomi OHBA,遠藤 久,Hisashi ENDO
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If the wireless communication is feasible in the concrete structure of power plants, it is effective for us to reduce the construction cost, improve the placement of equipment and change facilities easily. In buildings of such a power plant, the reinforced concrete (RC) walls might be more than one meter in thickness, with high rebar density. Therefore, radio wave transmission over this kind of concrete walls was studied to discuss feasibility. Aperture parts of walls, such as doors, whose thickness is ...
英字タイトル:
A feasibility study of the transmission radio wave over the reinforced concrete structure in the buildings of power plants for wireless network
第14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 (3) 配管支持構造物への適用事例
著者:
相澤 康介,Kosuke AIZAWA,髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO
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One of important mission of nuclear power plants (NPP) at R&D stage is to develop maintenance program for commercial reactors step by step securing safety. Basic principles of maintenance management for NPP at R&D stage were proposed. In this paper, applications for maintenance program on piping support of prototype sodium cooled fast breeder reactor Monju are studied on the basis of the proposed basic principles of maintenance management for NPP at R&D stage. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (3) Application to piping support
第14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 (4)ナトリウム弁の事例
著者:
近澤 佳隆,Yoshitaka CHIKAZAWA,髙屋 茂,Shigeru TAKAYA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO
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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 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, maintenance program for sodium valves are investigated. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (4) case study on sodium valves
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