• DocumentCode
    2154242
  • Title

    Recent progress from the DIII-D program

  • Author

    Kellman, A.G.

  • Author_Institution
    Gen. Atomics, San Diego, CA, USA
  • fYear
    2002
  • fDate
    2002
  • Firstpage
    442
  • Lastpage
    447
  • Abstract
    Significant progress has been made in a number of key scientific and engineering areas that are critical to advanced tokamak operation on the DIII-D tokamak. Improved error field correction coupled with plasma rotation has resulted in a passive wall stabilized discharge at twice the no-wall beta limit. Active feedback stabilization of the resistive wall mode (RWM) has been improved using newly installed internal magnetic sensors and external control coils. A set of internal control coils for RWM feedback has been designed that should permit operation at close to the ideal limit. Real-time stabilization of the neoclassical tearing mode has been achieved using a new "search and suppress" control algorithm coupled with electron cyclotron current drive (ECCD). The ECCD system is routinely providing in excess of 2 MW of power for 2 s pulses. Modeling predicts that measured efficiencies of ECCD are consistent with future, fully non-inductive AT target discharges. Massive injection of Ar gas has resulted in successful mitigation of disruptions in high performance discharges without producing high energy runaway electrons. Finally, an upgraded digital plasma control system will provide significantly more capability to provide real time measurement and control of plasma profiles and instabilities.
  • Keywords
    fusion reactor operation; plasma flow; plasma heating; plasma toroidal confinement; tearing instability; 2 MW; 2 s; Ar gas; DIII-D; ECCD; beta limit; control coils; electron cyclotron current drive; error field correction; neoclassical tearing mode; plasma instability; plasma profile; plasma rotation; resistive wall mode; search and suppress control algorithm; tokamak; Coils; Control systems; Cyclotrons; Electrons; Error correction; Feedback; Magnetic sensors; Plasma measurements; Predictive models; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 2002. 19th Symposium on
  • Print_ISBN
    0-7803-7073-2
  • Type

    conf

  • DOI
    10.1109/FUSION.2002.1027732
  • Filename
    1027732