• DocumentCode
    1603033
  • Title

    Power supply changes for NSTX Resistive Wall Mode Coils

  • Author

    Ramakrishnan, Shankar ; Neumeyer, C. ; Mozulay, R. ; Baker, Edwards ; Hatcher, R. ; Lawson, J. ; Que, W. ; Zhao, Xingang

  • Author_Institution
    Princeton Plasma Phys. Lab., Princeton, NJ, USA
  • fYear
    2013
  • Firstpage
    1
  • Lastpage
    5
  • Abstract
    The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physics Laboratory (PPPL). Most of the hardware, plant facilities, auxiliary sub-systems, and power systems originally used for the Tokamak Fusion Test Reactor (TFTR) have been used with suitable modifications to reflect NSTX needs. Prior to 2004, the NSTX power system was feeding twelve (12) circuits in the machine. In 2004 the Resistive Wall Mode (RWM) Coils were installed on the machine to correct error fields. There are six of these coils installed around the machine in the mid-plane. Since these coils need fast and accurate controls, a Switching Power Amplifier (SPA) with three sub-units was procured, installed and commissioned along with other power loop components. Two RWM Coils were connected in series and fed from one SPA sub-unit. After the initial RWM campaign, operational requirements evolved such that each of the RWM coils now requires separate power and control. Hence a second SPA with three sub-units has been procured and installed. The second unit is of improved design and has the controls and power components completely isolated. The existing thyristor rectifier is used as DC Link to both of the Switching Power Amplifiers. The controls for the RWM are integrated into the overall computer control of the DC Power systems for NSTX. This paper describes the design changes in the RWM Power system for NSTX.
  • Keywords
    Tokamak devices; fusion reactor design; fusion reactor instrumentation; nuclear electronics; plasma toroidal confinement; plasma-wall interactions; DC power systems; NSTX power system; NSTX resistive wall mode coils; National Spherical Torus Experiment; Princeton Plasma Physics Laboratory; Tokamak Fusion Test Reactor; auxiliary sub-systems; error fields; initial RWM campaign; plant facilities; power loop components; power supply changes; switching power amplifier; Capacitors; Coils; Feeds; Optical fiber cables; Optical switches; Power supplies;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
  • Conference_Location
    San Francisco, CA
  • Print_ISBN
    978-1-4799-0169-2
  • Type

    conf

  • DOI
    10.1109/SOFE.2013.6635283
  • Filename
    6635283