• DocumentCode
    1063983
  • Title

    Engineering and test of magnet systems for NET

  • Author

    Salpietro, E.

  • Author_Institution
    Max-Planck-Inst. fur Plasmaphys., Garching, West Germany
  • Volume
    24
  • Issue
    2
  • fYear
    1988
  • fDate
    3/1/1988 12:00:00 AM
  • Firstpage
    1295
  • Lastpage
    1298
  • Abstract
    The magnetic system of NET (Next European Torus) provides a framework inside which ignited plasmas can be confined while nuclear component testing is performed. The toroidal and poloidal field coils are superconducting, since the demonstration of the applicability of this technology to a fusion reactor is an important part of the NET objectives. The toroidal field coils´ winding pack is made of double pancakes realized by winding the conductor with dry glass in the final shape. The poloidal field coils are divided into two subsets, the central solenoid stack and the outer equilibrium coils. Superficially both subsets are similar in that both will consist of a 40-kA force flow. He-cooled superconducting conductor in a glass-fiber-reinforced epoxy matrix, and perform both equilibrium and transformer functions. However, because of different operating conditions (field and stress levels), it is expected that the coils will use different conductor designs.
  • Keywords
    Tokamak devices; fusion reactor theory and design; superconducting magnets; 40 kA; NET; conductor designs; equilibrium coils; fusion reactor; operating conditions; poloidal field coils; solenoid stack; superconducting magnet systems; test; toroidal field coils; transformer; winding pack; Conductors; Fusion reactors; Glass; Magnetic confinement; Performance evaluation; Plasma confinement; Superconducting coils; Superconducting magnets; System testing; Toroidal magnetic fields;
  • fLanguage
    English
  • Journal_Title
    Magnetics, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9464
  • Type

    jour

  • DOI
    10.1109/20.11475
  • Filename
    11475