• DocumentCode
    2760410
  • Title

    A frictionless steering mechanism for the Front Steering ECCD ITER Upper Port Launcher

  • Author

    Sanchez, F. ; Bertizzolo, R. ; Chavan, R. ; Henderson, M.A. ; Landis, J.D.

  • Author_Institution
    Centre de Recherches des Phys. des Plasmas, Ecole Polytech. Fed. de Lausanne
  • fYear
    2005
  • fDate
    Sept. 2005
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    A FS launcher is being designed for the ITER upper port, which offers enhanced physics performance over the RS launcher. A two mirror system is used to decouple the focusing and steering aspects of the launcher and provide a relatively small beam waist (<20 mm) projected far into the plasma (>1.6 m from the steering mirror). The resulting NTM stabilization efficiency (maximum CD density divided by the local bootstrap current >1.6) is above marginal for the q=2 and 3/2 rational flux surfaces of the relevant ITER equilibria (scenarios 2, 3a and 5) and a factor of ~3 relative to an equivalent RS launcher. The performance of the FS launcher strongly depends on the reliability of the steering mechanism, which is used to rotate the plasma facing steering mirror. CRPP has designed a frictionless steering mechanism assembled in a compact cartridge capable of up to plusmn7deg rotation (corresponding to a poloidal steering range of up to plusmn14deg for the microwave beam around a fixed axis of rotation) that offers a high operation reliability despite the close proximity to the thermal and neutron flux coming from the ITER plasma
  • Keywords
    Tokamak devices; fusion reactor design; fusion reactor ignition; neutron flux; plasma radiofrequency heating; tearing instability; CD density; CRPP; ECRH; ITER equilibria; ITER plasma; NTM stabilization efficiency; beam waist; bootstrap current; equivalent RS launcher; flexure pivot; focusing mirror; frictionless steering mechanism; front steering ECCD ITER upper port launcher design; high operation reliability; microwave beam; neutron flux; plasma facing steering mirror; poloidal steering range; rational flux surfaces; rotation fixed axis; thermal flux; Apertures; Assembly; Mirrors; Neutrons; Particle beam injection; Particle beams; Plasma density; Plasma properties; Plasma waves; Resonance; FS launcher; ITER ECRH; flexure pivot; front steering;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
  • Conference_Location
    Knoxville, TN
  • Print_ISBN
    0-4244-0150-X
  • Electronic_ISBN
    0-4244-0150-X
  • Type

    conf

  • DOI
    10.1109/FUSION.2005.252950
  • Filename
    4018984