• DocumentCode
    1094315
  • Title

    Progress in the 10-MW 140-GHz ECH System for the Stellarator W7-X

  • Author

    Thumm, M. ; Brand, P. ; Braune, H. ; Dammertz, G. ; Erckmann, V. ; Gantenbein, G. ; Illy, S. ; Kasparek, W. ; Laqua, H.P. ; Lechte, C. ; Leonhardt, W. ; Michel, G. ; Neffe, G. ; Piosczyk, B. ; Schmid, M. ; Weissgerber, M.

  • Author_Institution
    Inst. fur Hochleistungsimpuls- und Mikrowellentech., Karlsruhe
  • Volume
    36
  • Issue
    2
  • fYear
    2008
  • fDate
    4/1/2008 12:00:00 AM
  • Firstpage
    341
  • Lastpage
    355
  • Abstract
    During the last years, electron cyclotron heating (ECH) was proven to be one of the most attractive heating schemes for stellarators because it provides net-current-free plasma startup and heating. Both the stellarator Wendelstein 7-X (W7-X), which is under construction at the Max-Planck-Institut fu umlr Plasmaphysik, Greifswald, Germany, and the International Thermonuclear Experimental Reactor (ITER) tokamak, which will be built in Cadarache, France, will be equipped with a strong ECH and current-drive system. Both systems are comparable in frequency and have continuous-wave capability (140 GHz, 10 MW for W7-X and 170 GHz, 24 MW for ITER). The commissioning of the ECH plant for W7-X is well underway; the status of the project and the first integrated full-power test results from two modules are reported and may provide valuable input for the ITER plant. The ten gyrotrons at W7-X will be arranged in two subgroups symmetrically to a central beam duct in the ECH hall. The RF wave of each subgroup will be combined and transmitted by a purely optical multibeam-waveguide (MBWG) transmission line from the gyrotrons to the torus. The combination of five 1 MW gyrotron beams to one beam line with a power of 5 MW reduces the complexity of the system considerably. The single- and MBWG mirrors and the polarizers have been manufactured. Cold tests of a full-size uncooled prototype line delivered an efficiency exceeding 90%. The microwave power will be launched to the plasma through ten chemical-vapor-deposited-diamond barrier windows and in-vessel quasi-optical plug-in launchers, allowing each 1-MW RF beam to be steered independently. The polarization, as well as the poloidal and toroidal launch angles, will be adjusted individually to provide optimum conditions for different heating and current-drive scenarios.
  • Keywords
    Tokamak devices; cyclotron radiation; gyrotrons; plasma heating; stellarators; ECH system; International Thermonuclear Experimental Reactor; ITER tokamak; Max-Planck-Institut fur Plasmaphysik; W7-X; W7-X stellarator; Wendelstein 7-X; current-drive system; diamond barrier windows; electron cyclotron heating; frequency 140 GHz; gyrotrons; microwave power; net-current-free plasma startup; optical multibeam-waveguide transmission line; plasma heating; power 10 MW; torus; Cyclotrons; Electrons; Gyrotrons; Heating; Inductors; Plasmas; Radio frequency; Structural beams; Testing; Tokamaks; Electron cyclotron heating (ECH); high-power continuous-wave (CW) gyrotron; quasi-optical transmission; stellarator;
  • fLanguage
    English
  • Journal_Title
    Plasma Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0093-3813
  • Type

    jour

  • DOI
    10.1109/TPS.2008.917950
  • Filename
    4468688