DocumentCode :
2760393
Title :
The Design and Physics Performance of the ITER Upper Port ECH Front Steering Launcher
Author :
Henderson, M. ; Chavan, R. ; Heidinger, R. ; Ramponi, G. ; Saibene, G. ; Sanchez, F. ; Sauter, O. ; Shidara, H. ; Zohm, H.
Author_Institution :
Centre de Recherches en Phys. des Plasmas, Ecole Polytech. Fed. de Lausanne
fYear :
2005
fDate :
Sept. 2005
Firstpage :
1
Lastpage :
4
Abstract :
The purpose of the ITER electron cyclotron resonance heating (ECRH) upper port launcher will be to stabilize the neoclassical tearing mode (NTM) by driving currents (ECCD) locally inside either the q=3/2 or 2 island. In order to deposit current predominately inside the island, a narrow ECCD current deposition profile is required. Also, a wide steering range is desired for application of co-ECCD on the relevant flux surfaces over the wide spectra of possible ITER plasma equilibria. A front steering (FS) launcher has been designed for application on the ITER upper port, offering a wider poloidal steering angle (ges20deg) and a higher ECCD density (factor of 3.0 on average) than the presently planned remote steering (RS) launcher. The launcher is capable of injecting 16 MW per port (eight beams of 2.0 MW) using a two mirror system (1 focusing and 1 steering) for focusing and redirecting the beam towards either the q=3/2 or 2 flux surfaces for all envisioned plasma equilibria. The steering mechanism is bearing-free with flexure pivots, in a compact cartridge capable of plusmn12deg rotation (corresponding to a poloidal steering range of plusmn24deg for the microwave beam). The increased steering range enlarges the range in which the ECCD deposition can be applied, offering the potential to address other physics issues such as sawtooth, FIR or ELM control. The complete design concept and calculated ECCD performance for NTM stabilization will be presented
Keywords :
antennas in plasma; fusion reactor design; fusion reactor ignition; plasma radiofrequency heating; sawtooth instability; tearing instability; ECCD current deposition profile; ECCD density; ECRH; ELM control; FIR control; ITER design; ITER electron cyclotron resonance heating; ITER plasma equilibria; ITER upper port ECH front steering launcher; ITER upper port antenna; NTM stabilisation; beam focusing; bearing-free steering mechanism; flux surfaces; mirror system; neoclassical tearing mode; poloidal steering angle; remote steering launcher; sawtooth control; Cyclotrons; Electrons; Heating; Mirrors; Particle beam injection; Particle beams; Physics; Plasma applications; Plasma density; Resonance; ECRH; ITER; Launcher; NTM stabilisation;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
Conference_Location :
Knoxville, TN
Print_ISBN :
0-4244-0150-X
Electronic_ISBN :
0-4244-0150-X
Type :
conf
DOI :
10.1109/FUSION.2005.252949
Filename :
4018983
Link To Document :
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