Development of Long Pulse RF Heating and Current Drive for H-Mode Scenarios with Metallic Walls in WEST

被引:6
作者
Ekedahl, Annika [1 ]
Bourdelle, Clarisse [1 ]
Artaud, Jean-Francois [1 ]
Bernard, Jean-Michel [1 ]
Bufferand, Hugo [1 ]
Colas, Laurent [1 ]
Decker, Joan [1 ]
Delpech, Lena [1 ]
Dumont, Remi [1 ]
Goniche, Marc [1 ]
Helou, Walid [1 ]
Hillairet, Julien [1 ]
Lombard, Gilles [1 ]
Magne, Roland [1 ]
Mollard, Patrick [1 ]
Nardon, Eric [1 ]
Peysson, Yves [1 ]
Tsitrone, Emmanuelle [1 ]
Supra, Tore [1 ]
机构
[1] CEA, IRFM, F-13108 St Paul Les Durance, France
来源
RADIOFREQUENCY POWER IN PLASMAS | 2015年 / 1689卷
关键词
HYBRID CURRENT DRIVE; TORE-SUPRA; PROJECT; DESIGN; EVOLUTION; ANTENNAS; DIVERTOR;
D O I
10.1063/1.4936478
中图分类号
O59 [应用物理学];
学科分类号
摘要
The longstanding expertise of the Tore Supra team in long pulse heating and current drive with radiofrequency (RF) systems will now be exploited in the WEST device (tungsten-W Environment in Steady-state Tokamak) [1]. WEST will allow an integrated long pulse tokamak programme for testing W-divertor components at ITER-relevant heat flux (10-20 MW/m(2)), while treating crucial aspects for ITER-operation, such as avoidance of W-accumulation in long discharges, monitoring and control of heat fluxes on the metallic plasma facing components (PFCs) and coupling of RF waves in H-mode plasmas. Scenario modelling using the METIS-code shows that ITER-relevant heat fluxes are compatible with the sustainment of long pulse H-mode discharges, at high power (up to 15 MW/30 s at I-P = 0.8 MA) or high fluence (up to 10 MW /1000 s at IP = 0.6 MA) [2], all based on RF heating and current drive using Ion Cyclotron Resonance Heating (ICRH) and Lower Hybrid Current Drive (LHCD). This paper gives a description of the ICRH and LHCD systems in WEST, together with the modelling of the power deposition of the RF waves in the WEST-scenarios.
引用
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页数:8
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