• DocumentCode
    2114561
  • Title

    Automated calculation of DIII-D neutral beam availability

  • Author

    Phillips, J.C. ; Hong, R.M. ; Scoville, B.G.

  • Author_Institution
    Gen. Atomics, San Diego, CA, USA
  • fYear
    1999
  • fDate
    1999
  • Firstpage
    511
  • Lastpage
    514
  • Abstract
    The neutral beam systems for the DIII-D tokamak are an extremely reliable source of auxiliary plasma heating, capable of supplying up to 20 MW of injected power, from eight separate beam sources into each tokamak discharge. The high availability of these systems for tokamak operations is sustained by careful monitoring of performance and following up on failures. One of the metrics for this performance is the requested injected power profile as compared to the power profile delivered for a particular pulse. Calculating this was a relatively straightforward task, however innovations such as the ability to modulate the beams and more recently the ability to substitute an idle beam for one which has failed during a plasma discharge, have made the task very complex
  • Keywords
    fusion reactor design; fusion reactor ignition; fusion reactor operation; fusion reactor theory; plasma beam injection heating; plasma toroidal confinement; 20 MW; DIII-D neutral beam availability; DIII-D tokamak; NBI; automated calculation; auxiliary plasma heating; fusion reactor design; tokamak operations; Availability; Condition monitoring; Fault location; Heating; Particle beam injection; Particle beams; Plasma sources; Power system reliability; Technological innovation; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1999. 18th Symposium on
  • Conference_Location
    Albuquerque, NM
  • Print_ISBN
    0-7803-5829-5
  • Type

    conf

  • DOI
    10.1109/FUSION.1999.849890
  • Filename
    849890