DocumentCode :
11843
Title :
Implications of the TORE-SUPRA WEST-Project on Radio Frequency Additional 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, Jovita Gerardus Maria ; Moll
Author_Institution :
CEA, St. Paul-lez-Durance, France
Volume :
42
Issue :
3
fYear :
2014
fDate :
Mar-14
Firstpage :
879
Lastpage :
884
Abstract :
This year, TORE-SUPRA celebrated 25 years of operation. During this 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: lower hybrid current drive, ions and electrons 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-shaped axisymmetric tokamak with AC main chamber walls and an AC tungsten divertor, the W-for tungsten-Environment in Steady-state tokamak (WEST). This new facility has the objective to offer ITER a test bed for validating the relevant AC metallic technologies in D-shaped H-mode plasmas. In contrast to other metallic devices such as JET and ASDEX upgrade, WEST will rely only on RF additional power systems. A set of plasma scenarios have been identified, ranging from a high total RF power scenario up to 15 MW-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; fusion reactor reaction chamber; high-frequency discharges; plasma radiofrequency heating; plasma toroidal confinement; tungsten; AC main chamber walls; AC metallic technologies; AC tungsten divertor; ASDEX upgrade; D-shaped H-mode plasmas; D-shaped axisymmetric tokamak; ITER; ITER-relevant conditions; JET; RF power; TORE-SUPRA WEST-Project; W; actively cooled plasma facing components; electron cyclotron resonance heating; high fluence scenario; high total RF power scenario; ion cyclotron resonance heating; lower hybrid current drive; particle fluence; power 10 MW; power 12.3 MW; power 15 MW; power 2.8 MW; power heat fluxes; radiofrequency additional heating systems; steady-state discharge; steady-state heat loads; steady-state tokamak; superconducting magnets; superfluid helium; time 1000 s; time 3 s; time 30 s; time 380 s; 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.2014.2303886
Filename :
6750086
Link To Document :
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