• DocumentCode
    2077911
  • Title

    MHD equilibrium and stability considerations for high-aspect-ratio ARIES-I tokamak reactors

  • Author

    Peng, Y.K.M. ; Strickler, D.J. ; Hogan, J.T. ; Whitson, J.C. ; Bathke, C.G. ; Evans, K., Jr. ; Jardin, S.C. ; Klasky, M. ; Leuer, J.A.

  • Author_Institution
    Oak Ridge Nat. Lab., TN, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    1278
  • Abstract
    The requirements of (1) an external poloidal-field coil (PFC) system with minimum stored energy, (2) double-null divertor plasmas with elongated D shape, (3) adequate passive stabilization of plasma vertical displacement by a vacuum vessel located behind the blanket zone, and (4) an enhanced plasma beta limit in the first stability regime are incorporated in the Advanced Reactor Innovation and Evaluation Study-I (ARIES-I) concept for a high-field tokamak reactor with high aspect ratio (A=4.5). The plasma current and pressure profiles are also made consistent with enhanced bootstrap current and reduced current drive power by means of ion cyclotron wave or neutral beam injection. These lead to plasmas characterized by an elongation of 1.8 to the divertor X-point, a triangularity of 0.7, a safety factor of ~1.5, a safety factor at the edge >4, a plasma beta of ~2%, and a poloidal beta of ~0.5. With a plasma current of 11 MA, a toroidal field of 13 T at the major radius of 6.5 m, and over 3.5 m of clearance between the PFCs and the plasma edge, the stored energy in the PFC system ranges from 20 GJ during plasma operation at low beta, to 12 GJ during plasma operation at high beta
  • Keywords
    fusion reactor safety; plasma instability; plasma magnetohydrodynamics; plasma toroidal confinement; 12 GJ; 13 T; 20 GJ; ARIES-I tokamak reactors; MHD equilibrium; double-null divertor plasmas; elongation; first stability regime; high beta; high-aspect-ratio; ion cyclotron wave injection; low beta; neutral beam injection; passive stabilization; plasma beta limit; plasma current; plasma pressure; plasma vertical displacement; poloidal beta; poloidal-field coil; safety factor; stability; stored energy; triangularity; Coils; Elementary particle vacuum; Inductors; Magnetohydrodynamics; Plasma stability; Plasma waves; Safety; Shape; Technological innovation; Vacuum systems;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102446
  • Filename
    102446