DocumentCode :
65852
Title :
Implications of the Tore-Supra WEST-Project on Radio-Frequency Additionnal Heating Systems
Author :
Guilhem, D. ; Argouarch, A. ; Bernard, Jean-Michel ; Bouquey, F. ; Colas, L. ; Delpech, L. ; Durodie, F. ; Ekedahl, A. ; van Helvoirt, Jan ; Hillairet, J. ; Joffrin, E. ; Litaudon, X. ; Magne, R. ; Milanesio, Daniele ; Moerel, J. ; Mollard, P. ; Wittebol,
Author_Institution :
IRFM, CEA, St. Paul-lez-Durance, France
Volume :
42
Issue :
3
fYear :
2014
fDate :
Mar-14
Firstpage :
600
Lastpage :
605
Abstract :
This year Tore-Supra celebrated its 25 years of operation. During this long time, a number of technologies have been developed. First of all, it was mandatory to develop reliable superconducting magnets at ~ 1.8 K, with superfluid helium as an efficient coolant. For the production of steady state discharge, three types of radio frequency (RF) additional heating systems have been developed: 1) lower hybrid current drive; 2) ion cyclotron resonance heating; and 3) electron cyclotron resonance heating. To cope with long lasting discharges (up to 380 s ×2.8 MW) and large RF additional heating power (12.3 MW ×3 s), actively cooled (AC) plasma facing components were deployed in Tore-Supra for the first time in a tokamak environment. Tore-Supra is now being modified into a D-shape axisymmetric tokamak with AC tungsten main chamber walls and a divertor, the WEST project (W-for tungsten-environment in steady-state tokamak). This new facility has the objective to offer ITER a test bed for validating the relevant AC metallic technologies in D-shape H-mode plasmas. In contrast to other metallic devices, such as JET and ASDEX Upgrade, WEST will rely only on the RF additional power systems. A set of plasma scenarios have been identified, ranging from a high total RF power scenario up to 15 MW in 30 s, to a high fluence scenario of 1000 s with up to 10 MW of injected RF power. These scenarios are able to reproduce ITER relevant conditions of steady state heat loads of 10-20 MW/m2, to test tungsten AC divertor technologies with relevant power heat fluxes and particle fluence.
Keywords :
Tokamak devices; fusion reactor divertors; plasma boundary layers; plasma radiofrequency heating; plasma toroidal confinement; AC tungsten main chamber walls; D-shape H-mode plasmas; D-shape axisymmetric tokamak; RF additional power systems; Tore-Supra WEST-project; actively cooled plasma facing components; electron cyclotron resonance heating; hybrid current drive; injected RF power; ion cyclotron resonance heating; metallic devices; plasma scenarios; power heat fluxes; radio-frequency additionnal heating systems; steady state discharge production; superconducting magnets; superfluid helium; tokamak environment; tungsten AC divertor technologies; Antennas; Heating; Radio frequency; Steady-state; Tokamaks; Tungsten; Plasma additional heating systems; Tore-Supra; WEST-project; radio-frequency (RF);
fLanguage :
English
Journal_Title :
Plasma Science, IEEE Transactions on
Publisher :
ieee
ISSN :
0093-3813
Type :
jour
DOI :
10.1109/TPS.2013.2290429
Filename :
6716017
Link To Document :
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