Title :
First high-power tests of a remote steering concept for ECRH/ECCD at ITER
Author :
Gantenbein, G. ; Erckmann, V. ; Kasparek, W. ; Plaum, B. ; Laqua, H. ; Michel, G. ; Schwörer, K. ; Bruschi, A. ; Cirant, S. ; Gandini, F. ; Verhoeven, A.G.A.
Author_Institution :
Inst. fur Plasmaforschung, Stuttgart Univ., Germany
fDate :
27 Sept.-1 Oct. 2004
Abstract :
The major step in the development of tokamaks towards fusion power plants is the International Thermonuclear Experimental Reactor (ITER). This machine is equipped with an electron cyclotron resonance heating (ECRH) system which can be applied for very localised heating of the plasma or for current drive (ECCD) in the plasma. High power tests of a remote steering launcher system have performed successfully with a four side corrugated square waveguide operated under atmospheric pressure. The thermographic image of the beam on the absorbing screen and the heating of the waveguide wall during a long pulse shot waveguide has been recorded with an IR camera at 170 GHz.
Keywords :
Tokamak devices; fusion reactors; infrared imaging; millimetre wave imaging; plasma beam injection heating; plasma radiofrequency heating; waveguide antennas; 170 GHz; ECRH; IR camera; International Thermonuclear Experimental Reactor; Tokamaks; absorbing screen; atmospheric pressure; electron cyclotron current drive; electron cyclotron resonance heating; four side corrugated square waveguide; fusion power plants; high power tests; long pulse shot waveguide; plasma heating; remote steering concept; remote steering launcher system; thermographic image; Atmospheric-pressure plasmas; Cyclotrons; Electrons; Heating; Inductors; Plasma displays; Plasma waves; Power generation; Testing; Tokamaks;
Conference_Titel :
Infrared and Millimeter Waves, 2004 and 12th International Conference on Terahertz Electronics, 2004. Conference Digest of the 2004 Joint 29th International Conference on
Print_ISBN :
0-7803-8490-3
DOI :
10.1109/ICIMW.2004.1422071
