トカマクにおける強磁性体製真空容器の作る磁場の評価  [in Japanese] Evaluation of Magnetic Field due to Ferromagnetic Vacuum Vessel in Tokamak  [in Japanese]

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Author(s)

Abstract

We evaluated magnetic fields due to the ferromagnetic vacuum vessel(FVV)in the Hitachi Tokamak HT-2 experimentally and computationally, the results were extrapolated to the JFT-2M and ITER. The maximum amount of local poloidal field on the magnetic axis induced by the FVV port was about 5mT in the HT-2. This is the allowable amount of the field to discharge plasma in the HT-2. The proportion of external poloidal field shielded by FVV is in inverse proportion to external toroidal field. The stronger the field induced by FVV, the smaller the distance between plasma center and vacuum vessel wall. The delay time of poloidal field penetration due to the FVV is small, as long as the toroidal field is supplied.

Journal

  • Journal of plasma and fusion research

    Journal of plasma and fusion research 74(3), 274-283, 1998-03-25

    プラズマ・核融合学会

References:  12

Cited by:  2

Codes

  • NII Article ID (NAID)
    110003826199
  • NII NACSIS-CAT ID (NCID)
    AN10401672
  • Text Lang
    JPN
  • Article Type
    Journal Article
  • ISSN
    09187928
  • NDL Article ID
    4434925
  • 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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