• DocumentCode
    2724155
  • Title

    Start-up and early results from Alcator C-MOD

  • Author

    Fairfax, Stephen A.

  • Author_Institution
    Plasma Fusion Center, MIT, Cambridge, MA, USA
  • Volume
    2
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    812
  • Abstract
    Alcator C-MOD is a compact, high performance tokamak designed to address reactor-relevant issues including diverter operation, confinement, and auxiliary heating. It incorporates flexible shaping of non-circular, diverted plasmas, strong ICRF heating, and many innovative engineering features to achieve high performance in a compact device with modest cost. Like its predecessors, Alcator A and Alcator C, Alcator C-MOD uses cryogenically cooled copper magnets to produce high toroidal fields (9 Tesla at 0.67 m) and strong ohmic heating (up to 3 MA.) The thick wall of the vacuum vessel, while complicating the normal problems of plasma initiation and control, are relevant to virtually all next-generation designs. The facility operated briefly in late 1991 and again in early 1992, when a terminal failed on one of the PF magnets. The experiment resumed operations in May 1993. This report describes the start-up and early operational experience, comparing with both design scenarios and previous experience on Alcator A and C. Results from operations during the summer of 1993 are presented
  • Keywords
    fusion reactor design; fusion reactor operation; fusion reactors; plasma ohmic heating; plasma radiofrequency heating; plasma toroidal confinement; 3 MA; 9 T; Alcator C-MOD; Cu; auxiliary heating; compact high performance tokamak; cryogenically cooled magnets; design scenarios; diverter operation; flexible shaping; fusion reactor start-up; high toroidal fields; noncircular diverted plasmas; operational experience; plasma confinement; plasma control; plasma initiation; reactor-relevant issues; strong ICRF heating; strong ohmic heating; vacuum vessel; Copper; Costs; Heat engines; Heating; Magnetic confinement; Magnets; Plasma confinement; Plasma devices; Temperature control; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
  • Conference_Location
    Hyannis, MA
  • Print_ISBN
    0-7803-1412-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1993.518449
  • Filename
    518449