BLANKET DESIGN USING FLIBE IN HELICAL-TYPE FUSION-REACTOR FFHR

The blanket design for a force-free helical reactor (FFHR) is presente d, which is a demo-relevant heliotron-type D-T fusion reactor based on the first all-superconducting-coils device, LHD (large helical device ) under construction in NIFS at present. For the goal of a self-ignite d reactor of 3 GW thermal output, the design parameters at the first s tage for concept definition of FFHR have been investigated. The main f eature of FFHR is a force-free-like configuration of helical coils, wh ich makes it possible to simplify the coil supporting structure and to use a high magnetic field instead of high plasma beta. The other feat ure is the selection of molten-salt FLiBe as a self-cooling tritium br eeder for mainly safety reasons owing to the low tritium inventory, lo w reactivity with air and water, low pressure operation, and low MHD r esistance compatible with a high magnetic field. In particular, as com mon issues in fusion reactors, the FLiBe blanket system in FFHR is exp ressed in detail by showing engineering possibilities to overcome key issues on tritium permeation, material corrosion, heat transfer, opera tion pressure, etc. The basic design for maintenance and repair of the blanket is also discussed. (C) 1997 Elsevier Science B.V.