Thermal-hydraulic analysis of the dual-cooled waste transmutation blanket for the FDS

A conceptual structure design and the thermal-hydraulic analysis of the pressurized helium gas and LiPb eutectic dual-cooled waste transmutation blanket for the Fusion-Driven Sub-critical System (FDS), which is being designed for multi-purposes (transmuting nuclear wastes from fission power plants, breeding fissionable nuclear fuel for fission power plants and breeding tritium for sustainable operation) based on the Tokamak fusion core with the minor radius of 1 m, the major radius of 4 m, the elongation of 1.7 and the responding neutron wall loading of 0.5 MW/m2, have been presented