Study and thermal-hydraulic design of water cooled PFC for SST-1 tokamak

The plasma facing components (PFCs) are an important part of Steady State Superconducting Tokamak (SST-1) design. PFC of SST-1 consists of divertors, passive stabilizers, baffles and limiters are designed to be compatible for steady state operation. The main consideration in the design of the PFC is the steady state heat removal of up to 1 MW/m². During steady-state operation, the average heat loads on divertor and passive stabilizers are expected to be 0.6 and 0.25 MW/m² respectively. The PFC has been design to withstand the peak heat fluxes and also without significant erosion such that frequent replacement is not necessary. Design considerations included 2-D steady state and transient tile temperature distribution and resulting thermal loads in PFC during cooling. Coolant parameters necessary to maintain optimum thermal-hydraulic design, tile surface temperature, and tile fitting mechanism. A 2-D finite difference code has been developed to study of flow behavior and thermal response of PFC during cooling.