核融合炉機器の遠隔保守に関する開発の現状  [in Japanese] Current Status of Research and Development on Remote Maintenance for Fusion Components  [in Japanese]

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Abstract

プラズマ装置内での遠隔機器のみによる保守作業が1998年にJETにおいて世界で初めて実施されて以降,真空容器内機器の遠隔保守の重要性は増すばかりである.特に,将来の原型炉においては,その経済性を左右する重要な要素の一つでもある.現在建設中のITERにおいても,ブランケットやダイバータに対する真空容器内での保守作業は遠隔機器のみで行うことを予定しており,これを可能とするためのさまざまな装置・機器類の設計や要素試験等が進められてきた.本解説は,核融合炉機器の遠隔保守について,主にITERを例として,その開発の現状について紹介するものである.

Journal

  • Journal of plasma and fusion research

    Journal of plasma and fusion research 84(2), 100-107, 2008-02-25

    プラズマ・核融合学会

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Codes

  • NII Article ID (NAID)
    110006835271
  • NII NACSIS-CAT ID (NCID)
    AN10401672
  • Text Lang
    JPN
  • Article Type
    REV
  • ISSN
    09187928
  • NDL Article ID
    9392536
  • NDL Source Classification
    ZM35(科学技術--物理学)
  • NDL Call No.
    Z15-8
  • Data Source
    CJP  NDL  NII-ELS  NDL-Digital 
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