• DocumentCode
    2759859
  • Title

    Experimental Study of Pellet Delivery to the ITER Inner Wall through a Curved Guide Tube at Steady-State Pressure

  • Author

    Combs, S.K. ; Baylor, L.R. ; Caughman, J.B.O. ; Fehling, D.T. ; Foust, C.R. ; Maruyama, S. ; McGill, J.M. ; Rasmussen, D.A.

  • Author_Institution
    Oak Ridge Nat. Lab., TN
  • fYear
    2005
  • fDate
    Sept. 2005
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    Injection of solid hydrogen pellets from the magnetic high-field side will be the primary technique for depositing fuel particles into the core of International Thermonuclear Experimental Reactor (ITER) burning plasmas. This injection scheme will require the use of a curved guide tube to route the pellets from the acceleration device, under the divertor, and to the inside wall launch location. In an initial series of pellet tests in support of ITER, single 5.3-mm-diam cylindrical D2 pellets were shot through a mock-up of the planned ITER curved guide tube. Those data showed that the pellet speed had to be limited to ap300 m/s for reliable delivery of intact pellets. Also, microwave cavity mass detectors located upstream and downstream of the test tube indicated that ap10% of the pellet mass was lost in the guide tube at 300 m/s. The tube base pressure for that test series was ap10-4 torr. However, for steady-state pellet fueling on ITER, the guide tube will operate at an elevated pressure due to the pellet erosion in the tube. Assuming the present design values for ITER pellet fueling rates/vacuum pumping and a 10% pellet mass loss during flight in the tube, calculations suggest a steady-state operating pressure in the range of 10-20 torr. Thus, experiments to ascertain the pellet integrity and mass loss under these conditions have been carried out. Also, some limited test data were collected at a tube pressure of ap100 torr. No significant detrimental effects have been observed at the higher tube pressures. The new test results are presented and compared to the baseline data previously reported
  • Keywords
    deuterium; fusion reactor design; fusion reactor divertors; fusion reactor fuel; fusion reactor ignition; hydrogen; plasma diagnostics; D; H; ITER inner wall; ITER pellet fueling rates; International Thermonuclear Experimental Reactor burning plasmas; acceleration device; curved guide tube; divertor; fuel particles; inside wall launch location; magnetic high-field side; microwave cavity mass detectors; pellet delivery; pellet erosion; pellet mass; pellet speed; pellet tests; primary technique; single 5.3-mm-diam cylindrical D2 pellets; solid hydrogen pellet injection; steady-state operating pressure; tube base pressure; vacuum pumping; Acceleration; Fuels; Hydrogen; Inductors; Magnetic cores; Plasma accelerators; Plasma devices; Solids; Steady-state; Testing; ITER; curved guide tube; inner wall; pellet injection; plasma;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
  • Conference_Location
    Knoxville, TN
  • Print_ISBN
    0-4244-0150-X
  • Electronic_ISBN
    0-4244-0150-X
  • Type

    conf

  • DOI
    10.1109/FUSION.2005.252923
  • Filename
    4018957