• DocumentCode
    298237
  • Title

    Design of the TFTR TF coil alternate coolant system

  • Author

    Walton, G.R. ; Brooks, A. ; Harnsberger, D.A. ; Murray, H. ; Satkofsky, J.

  • Author_Institution
    Plasma Phys. Lab., Princeton Univ., NJ, USA
  • Volume
    1
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    325
  • Abstract
    The Tokamak Fusion Test Reactor (TFTR) toroidal field (TF) system consists of twenty coils which when operated with deionized water as the coolant has a maximum pulsed operating current and I2T of 73.3 kA and 5.4 E10 A2-s respectively. With deionized water as the primary coolant, the pulse repetition rate is 300 s, which is dependent upon the cooling system efficiency. Numerous small water leaks in several TF coils occurred which have adversely impacted machine operations. These leaks have resulted in a reduction of the TF coil´s resistance to ground. Various leak repair techniques have been successfully used. However, the leaks which cannot be exactly located have a history of reoccurring after repairs have been made. An alternative approach to coil cooling has been implemented which replaces the deionized water with a nonconductive fluid. This fluid should prevent the degradation of the coil resistance because it will retain its high dielectric strength, even if it wets the coil insulation. Perfluoroheptane was chosen from a number of dielectric fluids because of its compatibility with existing materials in the TF coil circuit, chemical and radiation stability, and environmental acceptability. This fluid has reduced thermal capacity which decreases the TF coil I2 T to 4.84 E10 A2-s with an increased repetition rate to 900 s
  • Keywords
    Tokamak devices; coils; cooling; fusion reactor design; fusion reactors; 73.3 kA; H2O; TFTR; Tokamak Fusion Test Reactor; coil resistance; cooling system; deionized water; dielectric fluid; leak repair; nonconductive fluid; perfluoroheptane; toroidal field coil; water leaks; Coils; Coolants; Cooling; Degradation; Dielectric breakdown; Fusion reactor design; History; Inductors; System testing; 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.1993.518341
  • Filename
    518341