PFC integration on Tore-Supra WEST divertor

Full text of publication follows. In the context of the Tokamak Tore Supra evolution, the CEA Cadarache aims at transforming it into a test bench for ITER plasma facing components. This project named WEST (Tungsten Environment in Steady state Tokamak) is especially focused on the divertor target. The modification of the machine, by adding two axisymmetric divertors will make feasible an H-mode, and an X-point close to the lower divertor. This environment will allow exposing the divertor components up to 20 MW/m² heat flux during long pulse. These specifications are well suited to test the actively cooled tungsten target elements, respecting the ITER design. One challenge in such machine evolution is to integrate components in an existing vacuum vessel in order to obtain the best achievable performance. The divertors coils are designed regarding the magnetic specifications, the plasma facing components are placed according to the plasma shape, and then the interfaces have to be managed regarding the remaining space. Moreover in this layer, many important smaller components have to be integrated as cooling pipes, magnetic diagnostics, gas injection, Langmuir probe, etc. This paper deals with the integrated design of ITER tungsten target elements into the WEST environment considering magnetic, electric, thermal and mechanical loads. The feasibility of installation and maintenance has to be strongly considered as PFC will be replaced several times. The ports size allows entering a 30 degrees sector of pre-installed tungsten targets which will be plugged as quickly and easily has possible. The main feature of steady state operations is the active cooling, which lead to have many embedded cooling channels and bulky pipes on the PFC module. It means to take care of the many connections and sealing between vacuum and water. (authors)