Design of a new ECRH launcher for FTU tokamak

Abstract The present ECRH launcher installed on a single equatorial port of FTU tokamak was designed to inject four beams independently steered continuously in poloidal direction and in a set of predetermined toroidal angles. The launching mirrors can be moved only shot by shot. New experimental programmes for control of MHD instabilities with ECH/ECCD and heating of over-dense plasmas with ECBW require new launcher respectively with fast-steerable mirrors and increased toroidal capabilities. The required scanning speed for tracking the rational surfaces in the FTU plasma is 1 cm in 10 ms in poloidal direction, while the maximum toroidal angle needed for O–X–B heating scheme is around ±40°. Two ECRH lines, feeding the old launcher, will be switched to the new launcher, located in a different equatorial position, capable of launching two independent beams from small movable mirrors in the plasma proximity. A control on the power deposition width will be achieved by changing the beam radius in the plasma using an optical system composed by two mirrors (zooming range 17–28 mm). Place has been reserved for future arrangements of additional components, e.g. a remote steering waveguide. A dedicated feedback control for the poloidal motion of the launching mirrors is being developed, in order to adapt the tracking of the power deposition location to the dynamic changes of magnetic surfaces in real-time. The maximum toroidal angle impacts strongly on the movable mirror design; dimensions (height around 90 mm, width around 54 mm) are limited by the port width (=80 mm) and the need to preserve the maximum steering angle. Since the mirrors will not be actively cooled, temperature control will be achieved by covering the backside with a high emissivity coating, to obtain an efficient radiative cooling. A detailed description of the launcher is presented in the paper.

[1]  A. Popov,et al.  2D Modeling of the O–X conversion in toroidal plasmas , 2008 .

[2]  J. Preinhaelter,et al.  Penetration of high-frequency waves into a weakly inhomogeneous magnetized plasma at oblique incidence and their transformation to Bernstein modes , 1973, Journal of Plasma Physics.

[3]  Giovanni Ramponi,et al.  Overview of the ITER EC upper launcher , 2008 .

[4]  C. Sozzi,et al.  ECRH antenna at 140 GHz on FTU Tokamak , 2001 .

[5]  Mizuki Sakamoto,et al.  Electron cyclotron current drive experiments in LHCD plasmas using a remote steering antenna on the TRIAM-1M tokamak , 2006 .

[6]  William Bin,et al.  A New Launcher for Real-Time ECRH Experiments on FTU , 2009 .

[8]  É. Suvorov,et al.  Effects of Two-Dimensional Inhomogeneity in O-X Mode Conversion in Tokamak Plasmas , 2008 .

[9]  E. Mjølhus,et al.  Coupling to Z mode near critical angle , 1984, Journal of Plasma Physics.

[10]  William Bin,et al.  High-Power Millimeter-Wave Calorimetric Beam Absorbers , 2008 .

[11]  Tomasz Rzesnicki,et al.  Advances in high power calorimetric matched loads for short pulses and CW gyrotrons , 2007 .

[12]  I. Bernstein,et al.  Waves in a Plasma in a Magnetic Field , 1958 .

[13]  S. Cirant Overview of Electron Cyclotron Heating and Electron Cyclotron Current Drive Launcher Development in Magnetic Fusion Devices , 2008 .

[14]  G. Granucci,et al.  ECH/ECCD Applications for MHD Studies and Automatic Control in FTU Tokamak , 2008 .

[15]  ECRH-Group,et al.  Resonant and Nonresonant Electron Cyclotron Heating at Densities above the Plasma Cutoff by O-X-B Mode Conversion at the W7-As Stellarator , 1997 .

[16]  W. Kasparek,et al.  Tests of a 105 Ghz prototype diplexer–combiner based on square corrugated waveguide , 2009 .

[17]  V. Erckmann,et al.  High-power microwave diplexers for advanced ECRH systems , 2009 .

[18]  S. Nowak,et al.  Three-dimensional propagation and absorption of high frequency Gaussian beams in magnetoactive plasmas , 1994 .