Abstract
With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907–12), the Tore Supra facility and team expertise (Dumont et al 2014 Plasma Phys. Control. Fusion 56 075020) is used to pave the way towards ITER divertor procurement and operation. It consists in implementing a divertor configuration and installing ITER-like actively cooled tungsten monoblocks in the Tore Supra tokamak, taking full benefit of its unique long-pulse capability. WEST is a user facility platform, open to all ITER partners. This paper describes the physics basis of WEST: the estimated heat flux on the divertor target, the planned heating schemes, the expected behaviour of the L–H threshold and of the pedestal and the potential W sources. A series of operating scenarios has been modelled, showing that ITER-relevant heat fluxes on the divertor can be achieved in WEST long pulse H-mode plasmas.
Highlights
Power exhaust is one of the main challenges for step fusion devices [1]
This paper describes the physics basis of WEST: the estimated heat flux on the divertor target, the planned heating schemes, the expected behaviour of the L–H threshold and of the pedestal and the potential W sources
The equilibria of figure 2 are used as references equilibria in the rest of the scenario study presented here. They are constrained by a fixed toroidal magnetic field BT = 3.7 T at 2.5 m and by an external radius of 2.93 m which is compatible with ion cyclotron resonance heating (ICRH) and lower hybrid current drive (LHCD) launchers positions
Summary
Power exhaust is one of the main challenges for step fusion devices [1]. In ITER and DEMO, the plasma facing. WEST provides an integrated platform for testing the ITER divertor components under combined heat and particle loads in a tokamak environment [2]. In the WEST actively cooled environment, there is no hard technological limit on the pulse duration, 1000 s is an indicative time scale
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