• DocumentCode
    2723727
  • Title

    Structural design of the superconducting poloidal field coils for the Tokamak Physics Experiment

  • Author

    O´Connor, T.G. ; Zbasnik, Jon P.

  • Author_Institution
    Lawrence Livermore Nat. Lab., CA, USA
  • Volume
    2
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    707
  • Abstract
    The Tokamak Physics Experiment concept design uses superconducting coils made from cable-in-conduit conductor to accomplish both magnetic confinement and plasma initiation. The Poloidal Field (PF) magnet system is divided into two subsystems, the central solenoid and the outer ring coils, the latter is focus of this paper. The eddy current heating from the pulsed operation is excessive for a case type construction; therefore, a “no case” design has been chosen. This “no case” design uses the conductor conduit as the primary structure and the electrical insulation (fiberglass/epoxy wrap) as a structural adhesive. The model integrates electromagnetic analysis and structural analysis into the finite element code ANSYS to solve the problem. PF coil design is assessed by considering a variety of coil current wave forms, corresponding to various operating modes and conditions. The structural analysis shows that the outer ring coils are within the requirements of the fatigue life and fatigue crack growth requirements. The forces produced by the Toroidal Field coils on the PF coils have little effect on the maximum stresses in the PF coils. In addition in an effort to reduce the cost of the coils a new elongated PF coil design was proposed which changes the aspect ratio of the outer ring coils to reduce the number of turns in the coils. The compressive stress in the outer ring coils is increased while the tensile stress is decreased
  • Keywords
    Tokamak devices; finite element analysis; fusion reactor design; fusion reactor materials; fusion reactors; nuclear engineering computing; superconducting coils; PF coil design; Poloidal Field magnet system; TPX; Tokamak Physics Experiment; cable-in-conduit conductor; coil current wave forms; conductor conduit; eddy current heating; electrical insulation; electromagnetic analysis; epoxy wrap; fatigue crack growth; fatigue life; fiberglass; finite element code ANSYS; magnetic confinement; maximum stresses; plasma initiation; structural adhesive; structural analysis; structural design; superconducting coils; superconducting poloidal field coils; tensile stress; Compressive stress; Conductors; Electromagnetic analysis; Fatigue; Magnetic confinement; Physics; Superconducting cables; Superconducting coils; Superconducting magnets; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
  • Conference_Location
    Hyannis, MA
  • Print_ISBN
    0-7803-1412-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1993.518426
  • Filename
    518426