• DocumentCode
    2037256
  • Title

    ITER in perspective

  • Author

    Henning, C.D.

  • Author_Institution
    Lawrence Livermore Nat. Lab., CA, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    481
  • Abstract
    The current International Thermonuclear Experimental Reactor (ITER) design features a 6-m major radius, a 2.15-m minor radius, and a 22-MA plasma current. About 330 V-s in the poloidal field system inductively drive the current for hundreds of seconds. About 125 MW of neutral-beam, lower-hybrid, and electron-cyclotron power are provided for steady-state current drive and heating. Because the ITER design must account for the fact that the tokamak database is not exact, a reasonably cautious approach must be taken. There are some benefits of such an approach: the chances of success are enhanced, ITER traverses most of the distance toward the size and power of a commercial reactor, and it may be capable of more performance than promised. By extending the operating rules to the maximum expected range, the fusion power may be increased such that the machine might be capable of simulating a small net energy condition. If so, then considerable progress could be made toward fusion-power applications
  • Keywords
    Tokamak devices; fusion reactor theory and design; ITER; International Thermonuclear Experimental Reactor; electron-cyclotron power; fusion-power; plasma current; poloidal field system; steady-state current drive; tokamak; Acceleration; Costs; Fusion reactor design; Inductors; Laboratories; Neutrons; Physics; Plasmas; Steady-state; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102268
  • Filename
    102268