• DocumentCode
    3169380
  • Title

    Current drive and heating systems for an ITER hard option

  • Author

    Lindquist, W. ; Bulmer, R. ; Fenstermacher, M. ; Nevins, W. ; Parker, J. ; Smith, G. ; Wendland, C. ; Williamson, V. ; Cooper, W. ; Wells, R.

  • Author_Institution
    Lawrence Livermore Nat. Lab., CA, USA
  • fYear
    1991
  • fDate
    30 Sep-3 Oct 1991
  • Firstpage
    919
  • Abstract
    A conceptual design was developed for a reference current drive and heating system for a HARD (high aspect ratio design) onion for ITER (International Thermonuclear Experimental Reactor). Twelve neutral beam modules, each rated at 1.3 MeV and 9.2 MW, perform plasma heating and current drive. An electron cyclotron system is used for initiating the plasma and for disruption control. An alternate system was defined, comprising a lower hybrid and ion cyclotron system for heating system for heating and current drive, augmented by the same electron cyclotron system proposed for the reference system. The neutral beam modules have been arranged in groups of three, two in a vertical array and one nested to the side. Four groups, and thus four ports, are required. Since a lower hybrid system is not needed for the HARD option, the two ports allocated for lower hybrid system in the CDA (conceptual design activity) are available. Therefore, the number of ports required for current drive and heating for the HARD option is five (4 neutral beams, 1 electron cyclotron) versus six (3 neutral beams, 2 lower hybrid, and 1 electron cyclotron) for the CDA. The neutral beam modules have been configured in sets of three, 2 in a vertical array, which has significantly reduced the overall height of the system
  • Keywords
    fusion reactor ignition; fusion reactor theory and design; plasma instability; plasma radiofrequency heating; plasma toroidal confinement; CDA; ITER hard option; International Thermonuclear Experimental Reactor; conceptual design; conceptual design activity; current drive; disruption control; electron cyclotron system; heating systems; high aspect ratio design; ion cyclotron system; lower hybrid; neutral beam modules; overall height; plasma heating; ports; reference system; vertical array; Cyclotrons; Electrons; Heating; Inductance; Laboratories; Particle beams; Plasma density; Plasma stability; Plasma temperature; Steady-state;
  • 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.1991.218699
  • Filename
    218699