• DocumentCode
    2646276
  • Title

    First tests of the new multi-frequency ecrh system at ASDEX upgrade

  • Author

    Leuterer, F. ; Wagner, D. ; Manini, A. ; Monaco, F. ; Münich, M. ; Ryter, F. ; Schütz, H. ; Zohm, H. ; Franke, T. ; Thumm, M. ; Heidinger, R. ; Gantenbein, G. ; Kasparek, W. ; Litvak, A.G. ; Popov, L.G. ; Nichiporenko, V.O. ; Myasnikov, V.E. ; Denisov, G.

  • Author_Institution
    EURATOM-IPP, Max-Planck-Inst. fur Plasmaphys., Garching
  • fYear
    2006
  • fDate
    4-8 June 2006
  • Firstpage
    133
  • Lastpage
    133
  • Abstract
    Summary form only given. The power deposition in ECRH (electron cyclotron resonance heating) of fusion plasmas is primarily determined by the magnetic field. For a single frequency ECRH system this has the consequence that for central heating the magnetic field is no longer a free parameter. However, for tokamak plasmas with different plasma currents or different equilibria, the magnetic field should be a free parameter in order to operate at a reasonable edge safety factor q(a). Furthermore, in a plasma with given parameters, some experimental features, like suppression of neoclassical tearing modes (NTM), require to drive current on the high field side without changing the magnetic field. These requests can be satisfied if the gyrotron frequency is variable. A new broadband ECRH system is currently under construction at the ASDEX Upgrade tokamak at IPP Garching. This system will employ multi-frequency gyrotrons which are step-tunable in the frequency range 105-140 GHz. In its final stage the system will consist of 4 gyrotrons with a total power of 4 MW and a pulse length of 10 s. It employs a fast steerable launcher in the plasma vessel for feedback controlled power deposition that allows for poloidal steering of 10 deg, within 100 ms. Transmission line elements, such as corrugated waveguides, polarizer mirrors and vacuum windows, are designed to cope for this frequency band. The first two-frequency gyrotron, operating at 105 GHz and 140 GHz, is currently being put into operation at ASDEX Upgrade
  • Keywords
    Tokamak devices; plasma boundary layers; plasma radiofrequency heating; plasma toroidal confinement; plasma transport processes; tearing instability; 10 s; 100 ms; 105 to 140 GHz; 4 MW; ASDEX Upgrade; ECRH; corrugated waveguides; edge safety factor; electron cyclotron resonance heating; feedback controlled power deposition; fusion plasmas; gyrotron frequency; magnetic field; neoclassical tearing modes; plasma currents; plasma vessel; polarizer mirrors; poloidal steering; steerable launcher; tokamak plasmas; transmission line elements; vacuum windows; Cyclotrons; Electrons; Frequency; Gyrotrons; Heating; Magnetic fields; Plasmas; System testing; Tokamaks; Variable speed drives;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Plasma Science, 2006. ICOPS 2006. IEEE Conference Record - Abstracts. The 33rd IEEE International Conference on
  • Conference_Location
    Traverse City, MI
  • Print_ISBN
    1-4244-0125-9
  • Type

    conf

  • DOI
    10.1109/PLASMA.2006.1707005
  • Filename
    1707005