• DocumentCode
    2726648
  • Title

    Installation and initial operation of the DIII-D advanced divertor cryocondensation pump

  • Author

    Smith, J.P. ; Schaubel, K.M. ; Baxi, C.B. ; Campbell, G.L. ; Hyatt, A.W. ; Laughon, G.J. ; Mahdavi, M.A. ; Reis, E.E. ; Schaffer, M.J. ; Sevier, D.L. ; Stambaugh, R.D. ; Menon, M.M.

  • Author_Institution
    Gen. Atomics, San Diego, CA, USA
  • Volume
    2
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    1043
  • Abstract
    Phase two of a divertor cryocondensation pump, the Advanced Divertor Program, is now installed in the DIII-D tokamak at General Atomics and complements the phase one biasable ring electrode. The installation consists of a 10 m long cryocondensation pump located in the divertor baffle chamber to study plasma density control by pumping of the divertor. The design is a toroidally electrically continuous liquid helium-cooled panel with 1 m2 of pumping surface. The helium panel is single point grounded to the nitrogen shield to minimize eddy currents. The nitrogen shield is toroidally continuous and grounded to the vacuum vessel in 24 locations to prevent voltage potentials from building up between the pump and vacuum vessel wall. A radiation/particle shield surrounds the nitrogen-cooled surface to minimize the heat load and prevent water molecules condensed on the nitrogen surface from being released by impact of energetic particles. Large currents (>5000 A) are driven in the helium and nitrogen panels during ohmic coil ramp up and during disruptions. The pump is designed to accommodate both the thermal and mechanical loads due to these currents. A feedthrough for the cryogens allows for both radial and vertical motion of the pump with respect to the vacuum vessel. Thermal performance measured on a prototype verified the analytical model and thermal design of the pump. Characterization tests of the installed pump show the pumping speed in deuterium is 42,000 l/sec for a pressure of 5 mTorr. Induction heating of the pump (at 300 W) resulted in no degradation of pumping speed. Plasma operations with the cryopump show a 60% lower density in H-mode
  • Keywords
    Tokamak devices; cryopumping; eddy currents; fusion reactor design; fusion reactor operation; fusion reactors; plasma density; shielding; 10 m; 300 W; 5 mtorr; Advanced Divertor Program; DIII-D advanced divertor cryocondensation pump; DIII-D tokamak; He; N; N-cooled surface; analytical model; biasable ring electrode; characterization tests; disruptions; divertor baffle chamber; eddy currents minimization; fusion reactor; fusion reactor design; induction heating; initial operation; ohmic coil ramp up; particle shield; plasma density control; pump installation; radiation shield; thermal performance; toroidally continuous shield; toroidally electrically continuous liquid He-cooled panel; Coils; Eddy currents; Electrodes; Helium; Nitrogen; Plasma density; Thermal loading; Tokamaks; Voltage; Water heating;
  • 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.1993.518501
  • Filename
    518501