Author/Authors :
Sagara، نويسنده , , A. and Yamanishi، نويسنده , , H. and Imagawa، نويسنده , , S. and Muroga، نويسنده , , T. and Uda، نويسنده , , T. and Noda، نويسنده , , T. and Takahashi، نويسنده , , S. and Fukumoto، نويسنده , , K. and Yamamoto، نويسنده , , T. and Matsui، نويسنده , , H. and Kohyama، نويسنده , , A. and Hasizume، نويسنده , , H. and Toda، نويسنده , , S. and Shimizu، نويسنده , , A. and Suzuki، نويسنده , , A. and Hosoya، نويسنده , , Y. and Tanaka، نويسنده ,
Abstract :
Blanket design is in progress in helical-type compact reactor FFHR-2. A localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR). Numerical results are presented on nuclear analyses using the MCNP-4B code, on thermal and stress analyses using the ABAQUS 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 construction of molten salt loop. Preliminary results in these experiments are also presented.
