• DocumentCode
    2934968
  • Title

    Advances in the operation of the DIII-D neutral beam computer systems

  • Author

    Phillips, J.C. ; Busath, J.L. ; Penaflor, B.G. ; Piglowski, D. ; Kellman, D.H. ; Chiu, H.K. ; Hong, R.M.

  • Author_Institution
    Gen. Atomics, San Diego, CA, USA
  • Volume
    2
  • fYear
    1997
  • fDate
    6-10 Oct 1997
  • Firstpage
    815
  • Abstract
    The DIII-D neutral beam system routinely provides up to 20 MW of deuterium neutral beam heating in support of experiments on the DIII-D tokamak, and is a critical part of the DIII-D physics experimental program. The four computer systems previously used to control neutral beam operation and data acquisition were designed and implemented in the late 1970´s and used on DIII and DIII-D from 1981-1996. By comparison to modern standards, they had become expensive to maintain, slow and cumbersome, making it difficult to implement improvements. Most critical of all, they were not networked computers. During the 1997 experimental campaign, these systems were replaced with new Unix compliant hardware and, for the most part, commercially available software. This paper describes operational experience with the new neutral beam computer systems, and new advances made possible by using features not previously available. These include retention and access to historical data, an asynchronously fired “rules” base, and a relatively straightforward programming interface. Methods and principles for extending the availability of data beyond the scope of the operator consoles will be discussed
  • Keywords
    Unix; data acquisition; fusion reactor design; fusion reactor ignition; fusion reactor operation; nuclear engineering computing; plasma beam injection heating; plasma toroidal confinement; 0 to 20 MW; D; DIII-D neutral beam computer systems operation; DIII-D tokamak; NBI heating; Unix compliant hardware; data acquisition; fusion reactors; neutral beam heating; programming interface; Computer displays; Computer networks; Control systems; Data acquisition; Hardware; Heating; Plasma displays; Power supplies; Power system reliability; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-4226-7
  • Type

    conf

  • DOI
    10.1109/FUSION.1997.687750
  • Filename
    687750