First high-power tests of a remote steering concept for ECRH/ECCD at ITER

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.