• DocumentCode
    3170889
  • Title

    SF6 and water cold trap for TFTR deuterium-tritium operations

  • Author

    Viola, M. ; Dudek, L. ; Garzotto, V. ; Kamperschroer, J. ; Martin, G. ; Rossmassler, R. ; Sissingh, R.

  • Author_Institution
    Plasma Phys. Lab., Princeton Univ., NJ, USA
  • fYear
    1991
  • fDate
    30 Sep-3 Oct 1991
  • Firstpage
    1004
  • Abstract
    The Tokamak Fusion Test Reactor (TFTR) vacuum system is being upgraded to trap SF6 gas which may leak from the neutral beam injectors during the planned deuterium-tritium experiments. This is necessary since SF6 can, in 25% of a gram-mole, completely inactivate the platinum catalyst in the tritium cleanup system (TCS). Any SF6 leaking into the injectors will initially be held on the liquid helium or liquid nitrogen cryopanels. During regens of the liquid helium panel, the deuterium and tritium will pass to the TCS, with the SF6 being retained on the cryopanels. In the final phase of the accident recovery scenario, the cryopanels will be warmed to room temperature and the SF6 collected by a liquid-nitrogen cooled cold trap. Design of the cold trap and measurements of the vapor pressure of SF6 at 77 K as a function of surface coverage are presented. The SF6 vapor pressure at 77 K, with only a few monolayers absorbed, was found to be <10-7 torr. Modest pressures of ~10-5 torr were measured after nearly 3×105 torr-1 were deposited on a cold trap with an area of 0.1 m2. In the final configuration, the cold trap will also be used to collect water which may have accidentally leaked into the vacuum system
  • Keywords
    Tokamak devices; fusion reactor theory and design; tritium handling; H2O; SF6; T cleanup system; Tokamak Fusion Test Reactor; accident recovery scenario; cooled cold trap; cryopanels; neutral beam injectors; tokamak fusion reactor; vacuum system; water; Accidents; Deuterium; Helium; Inductors; Nitrogen; Platinum; System testing; Temperature; Tokamaks; Vacuum systems;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-0132-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1991.218777
  • Filename
    218777