• DocumentCode
    298270
  • Title

    Installation, preoperational testing and initial operation of the TFTR neutral beam deuterium-tritium gas delivery system

  • Author

    Oldaker, M.E. ; Lawson, J.E. ; Wright, K.E.

  • Author_Institution
    Plasma Phys. Lab., Princeton Univ., NJ, USA
  • Volume
    1
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    487
  • Abstract
    The Gas Delivery System for the TFTR Neutral Beam (NB) Heating System has been replaced with a new system which permits injection of either hydrogen/deuterium or tritium into each of the twelve Long Pulse Ion Sources (LPIS). The new gas delivery system will provide throughputs up to 100 torr-l/s of deuterium or 50 torr-l/s of tritium to each of the LPISs. The desired gas can be selected and the throughput adjusted between pulses on an individual source basis. The throughput is maintained uniform to ±1% throughout the injection pulse by utilizing a closed loop controller which varies the voltage applied to a piezoceramic element within piezoelectric valve as a function of the measured pressure within individual local storage plenums. The capability to “condition” the LPISs with deuterium between tritium injection pulses and maximum operational flexibility is provided by installing independent deuterium and tritium subsystems on each LPIS, A programmable logic controller provides central control, interlocks and permissives for all twelve LPISs. This paper presents the final installation and the results from preoperational testing and initial operation of the Neutral Beam Deuterium-Tritium Gas Delivery System (NB D-T GDS)
  • Keywords
    Tokamak devices; fusion reactor design; ion sources; particle beam injection; plasma beam injection heating; D injection; Gas Delivery System; H injection; Long Pulse Ion Sources; NB D-T GDS; TFTR Neutral Beam Heating System; TFTR neutral beam deuterium-tritium gas delivery system; closed loop controller; deuterium subsystems; individual local storage plenums; initial operation; injection pulse; installation; maximum operational flexibility; piezoceramic element; piezoelectric valve; preoperational testing; programmable logic controller; tritium injection; tritium injection pulses; tritium subsystems; Deuterium; Heating; Hydrogen; Ion sources; Niobium; Pressure control; Pulse measurements; Testing; Throughput; Voltage control;
  • 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.1993.518378
  • Filename
    518378