| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 271774 | Fusion Engineering and Design | 2013 | 5 Pages |
•Thermo-hydraulic studies of plasma facing components.•Design of a PHTS.•Design studies of a tokamak cooling system.
In ITER, it is foreseen to use an actively-cooled tungsten (W) divertor likely from the beginning of operation. This Plasma Facing Component (PFC) will be subjected to high energy deposition during the plasma operations that severely limit component lifetime. Tungsten has been less extensively studied in tokamaks than carbon. Unlike most present day short pulse fusion devices, Tore Supra is able to reach the ITER pulse length and provide relevant discharges conditions for tungsten PFCs technology validation.A new upgrade of the machine aiming at testing a W divertor under the steady state heat fluxes is being studied in the framework of the WEST (Tungsten (W) Environment in Steady-state Tokamak) project.As the PFC requirements will change, the PFC Primary Heat transfer System (PHTS) must be upgraded. And, even if the injected power in the plasma will not be significantly increased for the WEST project, an upgrade of the Heat Rejection System (HRS) is also needed. This paper presents the studies carried out for these upgrades and the technical solutions to be implemented.
