Design and development of the Flibe blanket for helical-type fusion reactor FFHR

Blanket design is in progress in helical-type compact reactor FFHR-2. A loc alized blanket concept is proposed by selecting molten-salt Flibe as a self -cooling tritium breeder from the main reason of safety: low tritium solubi lity, low reactivity with air and water, low pressure operation, and low MH D resistance which is compatible with the high magnetic field design in for ce-free helical reactor (FFHR). Numerical results are presented on nuclear analyses using the MCNP-4B code, on thermal and stress analyses using the A BAQUS code, and heat exchange efficiency from Flibe to He. R&D programs on Flibe engineering are also in progress in material dipping-tests and in con struction of molten salt loop. Preliminary results in these experiments are also presented. (C) 2000 Elsevier Science B.V. All rights reserved.