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Studies on maintainability and repairability for Japan Sodium-cooled Fast Reactor (JSFR)

JSFRの保守・補修性向上策の検討

磯野 健一; 久保 重信; 近澤 佳隆; 堂崎 浩二*; 大矢 武明*; 由井 正弘*

Isono, Kenichi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Dozaki, Koji*; Oya, Takeaki*; Yui, Masahiro*

JSFR実証炉について、軽水炉並みにほぼ全ての構成要要素の保守補修を可能にすることを目標とし、主要機器である原子炉構造及び1次・2次主冷却システムを対象に保守・補修が困難な部位を抽出した。抽出した保守・補修困難部位について、改善策検討の原則を設定し、改善案を提案した。更に、改善した主要機器を統合してプラント概念を再構築し、それが実際の発電所として実現可能であるかを確認するため、系統成立性及び安全性確認等一連の評価を実施した。その結果、再構築した概念は750MWeの実証炉だけでなく1500MWeの実用炉にも採用できる見通しを得た。

Aiming at enabling maintenance and repair of almost all components in JSFR demonstration reactor to a level equivalent to that attained for the light water reactors, we identified a number of parts which have difficulty in maintenance and repair in main components of the reactor structure and the primary/secondary main coolant system. And we defined the criteria for design improvement and then provided candidates of improvement measures for the identified parts. Furthermore, we made a modification of the plant design in a consistent manner integrating the improvements investigated for each major component. A series of evaluations were conducted to check the feasibility as a power plant. As the result, we found that the concept could be adopted not only to the demonstration reactor (750 MWe) but to the commercial one (1500 MWe).

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