• DocumentCode
    1472845
  • Title

    The Determination of the Current Center Line of the TF Coils of ITER

  • Author

    Knaster, J. ; Baynham, E.

  • Author_Institution
    ITER Organ., St. Paul-lez-Durance, France
  • Volume
    20
  • Issue
    3
  • fYear
    2010
  • fDate
    6/1/2010 12:00:00 AM
  • Firstpage
    1475
  • Lastpage
    1478
  • Abstract
    Perturbations of the axial symmetry of the poloidal magnetic field in the order of of the toroidal magnetic field (5.3 T) might induce the occurrence of magnetic islands which could degrade plasma confinement and eventually lead to disruption. A weighted parameter of the lowest harmonics, the `3-mode´ index, is used as the figure of merit of ITER confinement capability with respect to possible magnet geometrical deformations and assembly errors. Three sets of correction coils will ensure that error fields are kept below the Three Mode Error Index (TMEI) during operation. Fabrication tolerances and assembly misalignments of the TF coils beyond specified values might become a relevant contributor to possible error fields in the magnetic configuration. An accurate determination of the coil current center line (CCL) is essential as the reference for survey operations during fabrication and final installation phases. The CCL will be defined geometrically as the barycenter of the conductor grooves of the winding pack, which will consist of seven, stacked D-shaped radial plates. However, it also seems feasible to reconstruct the CCL of the winding pack from magnetic measurements. A current of 1 kA circulating in the winding pack at room temperature will generate a magnetic field gradient of 0.07 mT/mm at 500 mm from the winding pack center. With an array of probes operated in flip mode and accurately mounted with respect to the WP fiducial marks the CCL can be determined with accuracy < +/-1 mm. The paper will evaluate the accuracy of both geometric and magnetic procedures for current center line definition.
  • Keywords
    Tokamak devices; plasma magnetohydrodynamics; plasma toroidal confinement; D-shaped radial plates; ITER confinement capability; TF coils; assembly errors; axial symmetry; coil current center line; correction coils; error fields; fabrication tolerances; final installation phases; flip mode; magnet geometrical deformations; magnetic configuration; magnetic field gradient; magnetic islands; plasma confinement; poloidal magnetic field; room temperature; three mode error index; toroidal magnetic field; winding pack center; Error fields; ITER; TF coils; magnetic measurements;
  • fLanguage
    English
  • Journal_Title
    Applied Superconductivity, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    1051-8223
  • Type

    jour

  • DOI
    10.1109/TASC.2009.2039863
  • Filename
    5447787