WEST Physics Basis

TLDR

Let's parse content. Background lines: - "[Background] With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng." - "[Background] 89 907–12), the Tore Supra facility and team expertise (Dumont et al 2014 Plasma Phys." These seem incomplete but basically background: WEST is a facility, built on Tore Supra, etc. So background: "WEST is a tungsten divertor test facility built on the Tore Supra tokamak, leveraging its long‑pulse capability and team expertise." Purpose/Mechanism line: "[Purpose, Mechanism] Fusion 56 075020) is used to pave the way towards ITER divertor procurement and operation." This indicates purpose and mechanism: The purpose is to pave way towards ITER divertor procurement and operation. Mechanism: using WEST to pave the way. Mechanism lines: - "[Mechanism] 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." - "[Mechanism] WEST is a user facility platform, open to all ITER partners." So mechanism: Implementation of ITER-like actively cooled tungsten monoblocks in Tore Supra, using long-pulse capability; open user facility.

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.