第17回
六ヶ所サイクル施設における施設管理に関する取り組み
著者:
仙 和樹,塚越 慶和,渡邉 富士雄,高坂 充,守屋 登康,(日本原燃)
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Due to amendments of Regulatory requirement in April 2020, it becomes mandatory to observe and evaluate for application design reprocessing business and approval of design and construction even a series of process for improvement. It also should include design and construction process which was defined by technical specification as to general maintenance management. This paper introduces new initiative about maintenance management at nuclear fuel cycle facility operated by Japan Nuclear Fuel LTD., in 2020....
英字タイトル:
The initiative about maintenance management at nuclear fuel cycle facility in Rokkasho
第11回
再処理設備の民間規格化の現状~機器の設計/建設・維持管理~
著者:
西村 洋一,Yoichi NISHIMURA,大鷹 暢彰,Nobuaki OTAKA,久保田 浩,Hiroshi KUBOTA,高坂 充,Makoto KOUSAKA
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1. はじめに日本原燃株が青森県六ヶ所村で事業を進めている 再処理設備は、国内初の商業プラントである。再処 理設備は、原子力発電所から発生する使用済燃料を 再処理し、再び原子燃料として利用できるようにウ ランとプルトニウムを取り出すことを主な目的とし ている。このことから、再処理設備は核燃料サイク ルを確立するための要となっている。 この再処理設備の設計・建設は、法律に基づき指 定、認可を受け商業運転に向け着実に進歩を遂げて いる。再処理設備の操業後、安全で安定した運転を維持 し、操業後に計画されている改......
英字タイトル:
The Status of Standardization for Nuclear Fuels Reprocessing Facilities - Design / Construction and Fitness-for-Service of Equipments -
第6回
再処理設備の設計・維持に係る規格化の状況
著者:
大枝 郁,Kaoru OEDA,加納 洋一,Youichi KANO,浜田 泰充,Yasumitsu HAMADA,高坂 充,Makoto KOUSAKA
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We have both the national technical standards and the japanese society standards, that is, the nuclear power generation facilities codes available for the japanese nuclear power plants in terms of design and fitness-for-service. They are already esta blished, systematized and incorporated in our regulations, so that chey are referred when the design or the inspections take place at the stage of plant construction and when nspections, evaluations and maintenance have to be carried out properly dur ing the o...
英字タイトル:
The Situation of Standardization about a Design / Fitness-for-Servicefor Nuclear Fuels Reprocessing Facilities
第11回
核燃料再処理施設における溶接補修工法の開発
著者:
甲斐 喬,Takashi KAI,鴨 和彦,Kazuhiko KAMO,渡邉 智裕,Tomohiro WATANABE,加納 洋一,Yoichi KANO,高坂 充,Makoto KOSAKA
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If leak trouble occurs at nuclear fuel reprocessing facility, repair welding procedure with short constructi on period is necessary to keep the safety of facility. As repair welding procedures, build-up welding proce dure and cover plate welding procedure have been developed. To get a good quality of repair welding joint wi thout lack of fusion and burn through into inside, heat box control is applied to these welding procedures....
英字タイトル:
Development of welding repair procedures for nuclear fuel reprocessing facility
第14回
社会インフラ診断へのPFMの適用検討
著者:
礒部 仁博,Yoshihiro ISOBE,藤吉 宏彰,Hiroaki FUJIYOSHI,松永 嵩,Takashi MATSUNAGA,小川 良太,Ryota OGAWA,匂坂 充行,Mitsuyuki SAGISAKA,松本 聡司,Satoshi MATSUMOTO,高坂 徹,Toru KOSAKA,吉村 忍,Shinobu YOSHIMURA
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Special attentions have been increasingly paid for the diagnosis of social infrastructures after the collapse of ceiling of Sasago tunnel of Chuo Expressway. It is reported that the main cause was due to the age-related degradation of chemical anchors. Chemical anchors are also frequently used in nuclear power stations. Here we have been trying to apply PFM (Probabilistic Fracture Mechanics) to the diagnosis of social infrastructures using Dr. Mainte, an integrated simulator to optimize maintenance activi...
英字タイトル:
A Study of Application of PFM (Probabilistic Fracture Mechanics) to the Diagnosis of Social Infrastructures ]
第13回
軽水炉保全最適化のための統合型シミュレータ Dr. Mainte による ヒューマンエラーの影響とその低減効果の検討 2
著者:
礒部 仁博,Yoshihiro ISOBE,匂坂 充行,Mitsuyuki SAGISAKA,小川 良太,Ryota OGAWA,松永 嵩,Takashi MATSUNAGA,高坂 徹,Toru KOSAKA,松本 聡司,Satoshi MATSUMOTO,吉村 忍,Shinobu YOSHIMURA
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Dr. Mainte, an integrated simulator for maintenance optimization of LWRs (Light Water Reactors) has been developed based on PFM (Probabilistic Fracture Mechanics) analyses in terms of safety, availability and economic efficiency, environmental impact and social acceptance. For the further improvement of maintenance activities, the importance of reducing human errors is often pointed out. Human errors are well recognized to be affected by mental stress conditions. Due to the amendment of Industrial Safe...
英字タイトル:
Effects of Human Error and its Reduction Analyzed by Dr. Mainte, Integrated Simulator of Maintenance Optimization of LWRs 2
第12回
軽水炉保全最適化のための統合型シミュレータDr. Mainte による ヒューマンエラーの影響とその低減効果の検討
著者:
礒部 仁博,Yoshihiro ISOBE,匂坂 充行,Mitsuyuki SAGISAKA,小川 良太,Ryota OGAWA,松永 嵩,Takashi MATSUNAGA,高坂 徹,Toru KOUSAKA,松本 聡司,Satoshi MATSUMOTO,吉村 忍,Shinobu YOSHIMURA
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Dr. Mainte, an integrated simulator for maintenance optimization of LWRs (Light Water Reactors) has been developed based on PFM (Probabilistic Fracture Mechanics) analyses. The concept of the simulator is to provide a decision-making system to optimize maintenance activities for representative components and piping systems in nuclear power plants totally and quantitatively in terms of safety, availability and economic efficiency, environmental impact and social acceptance. For the further improvement ...
英字タイトル:
Effects of Human Error and its Reduction Analyzed by Dr. Mainte, Integrated Simulator of Maintenance Optimization of LWRs
第14回
非破壊検査装置への応用を目指した臭化タリウム(TlBr)検出器による ステンレス鋼材を用いた応答特性評価
著者:
高坂 充,Makoto KOUSAKA,人見 啓太朗,Keitaro HITOMI,長野 宣道,Nobumichi NAGANO,石井 慶造,Keizou ISHII
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The nuclear fuels reprocessing facilities are required to perform appropriate maintenances for the ageing phenomena of the facilities. Development of non-destructive testing devices with high detection precision of the defects, small sizes, and lightweights are essential for testing the facilities. In this study, thallium bromide (TlBr) detectors, which have high absorption efficiency for gamma rays, are developed for the application to a radiographic testing (RT) device. The detector performance was...
英字タイトル:
Response evaluation of thallium bromide (TlBr) detectors for non-distractive testing using stainless steel materials