Liquid surface divertor designs for fusion reactors

As part of work in the US on free flowing liquid surfaces facing the plasma, we are studying issues of integrating a liquid surface divertor into a configuration based upon an advanced tokamak (ARIES-RS) with the flow of the liquid first wall of molten salt Flinabe (Li, Na, Be fluorides) continuing to become the divertor. We present the design and thermal performance and issues in design integration such as the interactions with the plasma edge. Sn and Sn-Li have also been considered, although the complicated 3-D MHD flows cannot yet be fully modeled.