第16回
ケーブルトレイの1時間耐火仕様の検討
著者:
川井 貴弘,水野 道太,加藤 寿宏,辰巳 義和,(中部電力)
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Among the fire protection measures in nuclear power plants, the fireproof performance of the fireproof partition installed for system separation is required to satisfy the fire endurance test based on the Building Standard Law. In this time, we report on the result of examining the specification of the fireproof material and the attachment method to the cable tray etc. For the fireproof partition (1 hour fireproof) installed in the cable tray that satisfies the above requirements....
英字タイトル:
Examination of 1 hour fireproof specification of cable tray
第16回
シビアアクシデント時に発生する異物による非常用炉心冷却系ストレーナ圧損評価
著者:
嶋田 優雅,川井 貴弘,松田 真一,大山 正孝,堀井 一明,,(中部電力)
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公開日:
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ECCS strainer for Hamaoka NPP employs cassette type. At the time of severe accident, it is necessary to take into consideration the chemical debris which has not been considered in BWR so far, in order to carry out pH control in the reactor containment vessel. In this paper, we report the results of closed vertical pipe loop test on the evaluation of the ECCS strainer head loss when considering the chemical debris in addition to the debris such as coating generated at the time of severe accident....
英字タイトル:
Evaluation of ECCS strainer head loss caused by debris generated at the time of severe accidents.
第15回
ボルト簡易診断法の開発研究(2)
著者:
松井 計雄,(中部電力),礒部 仁博,藤吉 宏彰,小川 良太,(原燃工)
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公開日:
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We have developed a simplified diagnosis method of hammering inspection using AE (Acoustic Emission) sensor applicable to chemical anchors in nuclear power plants. The database was created to identify improper installation and aging of the anchors. We have also confirmed its applicability to other types of anchor (e.g. anchor bolts, mechanical anchors). The details of development process are described in this paper....
英字タイトル:
Developing a simplified diagnosis method for anchor bolts (2)
第15回
中央制御室床下ケーブルピット内における消火システムの検討
著者:
川井 貴弘,水野 道太,加藤 寿宏,辰巳 義和,(中部電力),西垣 洋一,溝口 浩一郎,片平 保司,(エア・ウォータ防災)
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公開日:
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Cable pit under the floor of the main control room of the nuclear power plant is structured as a small section so as to physically separate cables with different safety classifications. This time, a part of cable pit under the floor, which is a narrow and complicated structure, was mocked up and a test was conducted assuming the occurrence of fire at various places in the cable pit. Experiments confirmed the fluidity of smoke and fire extinguishing performance (diffusion and retention state of extinguishing...
英字タイトル:
Consideration of fire extinguishing system inside cable pit under main control room
第16回
保全テンプレートのあり方検討
著者:
鈴木 直浩,森山 泰之,(中部電力)
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Maintenance engineers are optimizing the maintenance of maintenance target equipment in the activities of Preventive Maintenance Optimization (PMO). This optimization activity needs to be reviewed on the basis of the previous operation and maintenance experience, and there is a "maintenance template" as a tool that can assist it appropriately and efficiently. We have discussed the utilization of maintenance templates in Japan as an important tool to show the optimization of maintenance, and the way of its u...
英字タイトル:
Discussion for Role of the Maintenance Template in Japan
第17回
原子力プラントのヒートバランスモデルの構築
著者:
稲垣 博光,榊原 玄大,(中部電力),山田康二,(JERA)
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A study was conducted to apply a performance management method based on heat balance, which is used to detect the causes of efficiency deterioration and equipment abnormalities in thermal power plants, to nuclear power plants. A heat balance model was created for Hamaoka Nuclear Power Station Unit 4, and problems such as calculation problems due to errors in actual operation data and difficulty in calculating the amount of energy due to moist steam were solved....
英字タイトル:
Construction of Heat Balance Model for Nuclear Power Plant
第16回
原子力発電所の保守管理規程/指針(JEAC4209/JEAG4210)改定の検討状況
著者:
鈴木 直浩,(中部電力),笠毛 誉士,(九州電力),真壁 知宏,(東京電力HD),中廣 雄一,(関西電力),堀水 靖,(JANSI)
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Principles of Nuclear Power Station's maintenance was established as Code for Maintenance at Nuclear Power Plants (JEAC 4209) in 2003 and revised in 2007,2014 And also Guide for Maintenance at Nuclear Power Plants was established in 2007 and revised in 2014. Recently these Code & Guide were revised accordingly and published as JEAC4209-2016 and as JEAG 4210-2016. Revising these Code & Guide are now under review. Points of the revision is to implement the new regulatory inspection system enforced in 2020 ref...
英字タイトル:
Progress report of Revising Code and Guide for Maintenance at Nuclear Power Plants
第16回
原子核乾板による浜岡2号機格納容器下部の観測(その2)
著者:
森島 邦博,中村 光廣,(名古屋大),辻 建二,田畑 邦浩,(中部電力)
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Muon radiography is one of the remote sensing technologies, and it has been used at Fukushima Daiichi NPP to understand the status of the fuel inside the reactor. Nuclear Emulsion is one of the detectors used for muon radiography. Its features are light weight, compact size, no power supply required, high position resolution, and suitable for installation in a limited space. So far, at the Hamaoka NPP, from the floor on the second underground level and the sub-drain in the building-outdoor part, observation...
英字タイトル:
Measurement of lower part of PCV of Hamaoka NPP with nuclear emulsion (Part2)
第17回
原子炉内表面に発生した孔食の溶接補修
著者:
熊野 秀樹,岡田 英雄,(中部電力),遠藤 友則,岡野 成威,望月 正人,(大阪大)
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Hamaoka nuclear power plant unit-5 had the sea water intrusion incident in 2011 during the shut-down process. We, Chubu electric power company, have conducted some researches for unit-5 re-start, since we had some concerns about the aftercare of pitting corrosions occurred in the inner surface of RPV. The aftercare includes the determination of whether corrosion pitting might propagate until RPV, determination of whether or not to clean Chloride ions in corrosion pits and the determination of need for weld ...
英字タイトル:
Weld repair of sea water induced corrosion pits in inner RPV surface
第16回
原子炉圧力容器内面の腐食に関する検討(2)SCC試験
著者:
熊野 秀樹,田畑 邦浩,鍾 祥玉,庄子 哲雄,(中部電力)
発刊日:
公開日:
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An inside cladding of RPV in Hamaoka-5 caused pitting damage by sea water intrusion in 2011. For a restart of Hamaoka-5, we need a conservative evaluation such that SCC propagates instead of pitting. Two years ago, we reported metallurgical observation results in advance of SCC tests at AESJ conference. This is the progress report describing SCC test results obtained after the AESJ conference....
英字タイトル:
A study on corrosion immunity of RPV inside cladding (2) Stress corrosion cracking test