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

摘要: Blanket design is in progress helical-type compact reactor FFHR-2. A localized blanket concept proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low solubility, reactivity with air and water, pressure operation, MHD resistance which compatible high magnetic field force-free helical (FFHR). Numerical results are presented on nuclear analyses using MCNP-4B code, thermal stress ABAQUS heat exchange efficiency to He. R&D programs engineering also material dipping-tests construction molten salt loop. Preliminary these experiments presented.