• DocumentCode
    298207
  • Title

    The configuration development and integration of the TPX device

  • Author

    Brown, T.G.

  • Author_Institution
    Plasma Phys. Lab., Princeton Univ., NJ, USA
  • Volume
    1
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    173
  • Abstract
    The TPX configuration was designed to meet the physics objectives and subsystem requirements in an arrangement that allowed access for remote maintenance. The steady state operations of TPX favored the use of superconducting magnets for both the toroidal and poloidal field systems. The desire to react the TF centering and overturning forces in a simplified wedged system lead to a TF case concept incorporating “two-coil” TF modules in a 90° four-coil quadrant arrangement. Low ripple and tangential plasma access to accommodate TFTR neutral beams were leading factors in determining the size and number of TF coils. The need for a large amount of space for the divertor and first wall component coolant services further influenced the shaping of the vacuum vessel. Additional configuration influences included: low activation considerations, divertor pumping, remote maintenance requirements, service access and compatibility with the existing TFTR text cell facility. The TPX configuration development and integration process has evolved through the conceptual design period and is now ready to enter the Preliminary Design Phase of the project. This paper describes the status of the configuration development and integration of the major TPX tokamak subsystems components
  • Keywords
    Tokamak devices; fusion reactor design; fusion reactors; TF centering; TFTR neutral beams; TPX device; configuration development; divertor pumping; first wall component coolant; four-coil quadrant; g, remote maintenance requirements; integration; low activation considerations; low ripple; poloidal field systems; remote maintenance; simplified wedged system; steady state operations; superconducting magnets; tangential plasma; toroidal field systems; two-coil TF modules; vacuum vessel; Laboratories; Magnetic materials; Physics; Plasma devices; Steady-state; Superconducting coils; Superconducting magnets; Titanium; Tokamaks; Toroidal magnetic fields;
  • 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.1993.518309
  • Filename
    518309