EC加熱用ジャイロトロンの高出力化と高効率化  [in Japanese] Development of High Power and High Efficiency Gyrotron for Electron Cyclotron Heating  [in Japanese]

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Author(s)

Abstract

Gyrotron is the heart of the ECH system for heating and current drive of tokamak fusion reactor. Recent progress of the gyrotron development in Japan (JAERI/Toshiba), Russia (Gycom) and USA (Varian) initiated the 170GHZ, 1MW, CW high efficiency gyrotron development for ITER. Key technologies of the high efficiency, high power, long pulse gyrotron development are described. The energy recovery gyrotron which recently achieved 50% efficiency in JAERI is mainly described as an example of the development.

Journal

  • Journal of plasma and fusion research

    Journal of plasma and fusion research 71(1), 5-14, 1995-01-25

    プラズマ・核融合学会

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Codes

  • NII Article ID (NAID)
    110003826954
  • NII NACSIS-CAT ID (NCID)
    AN10401672
  • Text Lang
    JPN
  • Article Type
    Journal Article
  • ISSN
    09187928
  • NDL Article ID
    3599617
  • NDL Source Classification
    NG1(原子炉)
  • NDL Source Classification
    ZM35(科学技術--物理学)
  • NDL Call No.
    Z15-8
  • Data Source
    CJP  CJPref  NDL  NII-ELS  NDL-Digital 
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