小型トカマクHT-2へのフェライト鋼適用  [in Japanese] Application of Ferritic Steel to Small Tokamak HT-2  [in Japanese]

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Author(s)

Abstract

A discharge test in HT-2 tokamak with ferritic steel first wall is summarized in this article. The ferritic plates were placed to simulate ferritic vacuum vessels. The local magnetic field due to magnetization around the port of the vacuum vessel can be reduced by TFC ripple and optimization of the shape of ferritic steel. No difficulties were observed in the discharge test, and normal HT-2 plasma discharge was obtained. Thus, we concluded that ferritic steel vacuum vessels are possible for fusion devices.

Journal

  • Journal of plasma and fusion research

    Journal of plasma and fusion research 74(5), 455-462, 1998-05-25

    プラズマ・核融合学会

References:  15

Codes

  • NII Article ID (NAID)
    110003826209
  • NII NACSIS-CAT ID (NCID)
    AN10401672
  • Text Lang
    JPN
  • Article Type
    ART
  • ISSN
    09187928
  • NDL Article ID
    4475568
  • 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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