• DocumentCode
    887670
  • Title

    Overview of the TFTR Computer System

  • Author

    Davis, S.L. ; Sauthoff, N.R. ; Stark, W.

  • Author_Institution
    Princeton University Plasma Physics Laboratory (PPPL) Princeton, New Jersey 08544
  • Volume
    34
  • Issue
    4
  • fYear
    1987
  • Firstpage
    718
  • Lastpage
    722
  • Abstract
    The Tokamak Fusion Test Reactor (TFTR) is an experimental device built to study the physics and engineering problems of magnetically confined plasmas with temperatures and densities close to those that would exist in an actual fusion reactor. One of the prime goals of TFTR is to reach scientific breakeven, which is defined as the point where the amount of power used to maintain plasma temperatures is equal to the amount of power released through fusion reactions. The purpose of this paper is to give an overview of the computer system that provides the control, monitoring, data collection and analysis functions for TFTR.
  • Keywords
    Inductors; Magnetic confinement; Magnetic devices; Maintenance engineering; Physics; Plasma confinement; Plasma temperature; Power engineering and energy; Testing; Tokamaks;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.1987.4334722
  • Filename
    4334722