Performance and design definition of the WEST Tokamak divertor coils power supplies

The main objective of the WEST project is to test the actively cooled tungsten plasma facing components under high flux conditions and to provide relevant information to ITER [1]. In this framework, two new power supplies will be installed in Tore Supra in order to feed the new upper and lower divertor coils. These new coils are installed inside the vacuum vessel to modify the magnetic configuration (X point) and to allow long pulse operation in H-mode. With a no load voltage of 405V, each power supply will be able to deliver up to 13kA during long pulses of 1000s every hour, or 20kA during short pulses of 10s every twenty minutes. The development of these power supplies is done through the frame of a partnership between CEA and SWIP (SouthWestern Institute of Physics, China). This paper presents the validation of the power supply structure regarding both electrical rating and plasma position control. A model with coupled electrical circuit and the model for plasma position rebuilding, shows the efficiency of the plasma position control. The electrical design of power supplies including voltage filters and protective devices and the progress status of the power supplies manufacturing phase in China are also presented.