High power heating and current drive experiments with EC waves in FTU tokamak

Details High power heating and current drive experiments with EC waves in FTU tokamak High power heating and current drive experiments with EC waves in FTU tokamak

Sep 1999

adsabs.harvard.edu/cgi-bin/nph-data_query?bibcode=1999aipc..485..221c&link_type=abstract

The thirteenth topical conference on radio frequency power in plasmas. AIP Conference Proceedings, Volume 485, pp. 221-228 (199

Computer Science

4

Plasma Heating By Particle Beams, Tokamaks, Spherical Tokamaks, Theory, Design, And Computerized Simulation

Scientific paper

The EC system at 140 Ghz, 2 MW, being implemented on FTU tokamak for performing electron heating, profile control and current drive, is composed by four gyrotrons with 0.5 s pulse length capability, and four hybrid mirror/waveguide transmission lines. The launching system is capable of poloidal/toroidal beam steering through a set of tiltable in-vacuum mirrors, coupling to the O-mode at the fundamental resonance, with full control of the e.m. field polarization. Experiments have been made with two gyrotrons, by launching 0.8 MW to the plasma. In the high density regime (local ne from ~0.8 up to 2 1020 m-3) the e-i energy transfer is significant, and ion heating is observed through the enhancement of the neutron emission in Deuterium plasmas. The highest electron heating is observed when on-axis ECRH is performed in the current ramp-up, sawtooth-free phase. In steady-state conditions, saw-tooth period is increased up to stabilization by off-axis ECRH. Localized ECCD is also performed to assist in the shaping of the current density profile.

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