• DocumentCode
    3170777
  • Title

    Plasma startup of the ARIES-III second stability advanced fuel tokamak

  • Author

    Emmert, G.A. ; Mogahed, E.A. ; Kessell, C. ; Mandrekas, J. ; Mau, T.-K.

  • Author_Institution
    Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA
  • fYear
    1991
  • fDate
    30 Sep-3 Oct 1991
  • Firstpage
    1031
  • Abstract
    The ARIES-III conceptual reactor design utilizes D-3He fuel in a second stability tokamak configuration. The process of starting up the plasma and bringing it to the desired operating point was analyzed using a time-dependent particle and power balance code in conjunction with MHD (magnetohydrodynamic) equilibrium and stability, and neutral beam current drive calculations. Two different startup scenarios, one using D-T to assist reaching the D-3He operating point and one using only pure D-3He, were analyzed. In order to minimize the amount of ICRF (ion cyclotron range of frequencies) auxiliary heating required, one must program the plasma current so that the plasma enters second stability as soon as practical; it was assumed that confinement improves greatly when the plasma is in second stability. Seeding the plasma with tritium during startup reduces the amount of ICRF power required, but leads to a 14-MeV neutron pulse. The blanket and magnet heating due to this neutron pulse are within acceptable limits. The DT assisted startup was chosen as the reference procedure. Pure D-3He startup of ARIES-III can be achieved with 200 MW of heating power in addition to that available from the current drive system
  • Keywords
    Tokamak devices; fusion reactor ignition; fusion reactor theory and design; ARIES-III second stability advanced fuel tokamak; MHD; auxiliary heating; neutral beam current drive; plasma current; startup scenarios; tokamak fusion reactor; Fuels; Heating; Helium; Inductors; Magnetic analysis; Magnetic confinement; Magnetohydrodynamics; Neutrons; Plasma confinement; Plasma stability;
  • 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.1991.218771
  • Filename
    218771