• Title of article

    Design and manufacture of the Poloidal Field Conductor Insert coil

  • Author/Authors

    Sborchia، نويسنده , , C. and Duglue، نويسنده , , D. and Hurd، نويسنده , , F. and Maix، نويسنده , , R. and Salpietro، نويسنده , , E. and Testoni، نويسنده , , P. and Bessette، نويسنده , , D. and Mitchell، نويسنده , , N. and Okuno، نويسنده , , K. and Sugimoto، نويسنده , , M. and Alekseev، نويسنده , , A. and Sytnikov، نويسنده , , V.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2003
  • Pages
    6
  • From page
    1081
  • To page
    1086
  • Abstract
    The Poloidal Field (PF) coils of ITER (International Thermonuclear Experimental Reactor) will supply the necessary magnetic field to initiate, shape, control and shutdown burning plasmas. The PF coils use NbTi cable-in-conduit superconductors, which operate at maximum currents of the order of 45–60 kA and experience large variations of current and magnetic fields. In order to test full-scale NbTi superconductors at operational conditions similar to ITER, the European Team has been asked to design and manufacture a PF conductor insert (PFCI). The cable has been provided by the Russian Federation. The Insert will be tested in 2004 in the Central Solenoid Model Coil (CSMC) facility at JAERI Naka, Japan.
  • Keywords
    ITER , Poloidal field coils , NbTi cable in-conduit
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2003
  • Journal title
    Fusion Engineering and Design
  • Record number

    2369473