Conceptual design of a power-producing fusion-fission hybrid reactor was carried out based on the new concept of the blanket containing equilibrium fissile fuel. The blanket safety performance was analysed on residual heat removal and accidental criticality. The concept of a direct enrichment fusion breeder blanket using UO2 powder was also presented and studied.The impact of uncertainties in neutron cross section data on design parameters such as tritium breeding ratio was analysed including the uncertainties of the secondary angular and energy distribution of neutrons. The uncertainty of the tritium breeding ratio due to cross-sections is about 6% for a commercial tokamak reactor. The errors of the design parameters due to the approximations in the multigroup transport calculation were also quantitatively estimated. The methods for the analyses were developed.The computer codes for nuclear analysis and design were developed. Those are: (1) BISON for one-dimensional transport and burnup calculation, (2) SUSD for the cross section sensitivity and uncertainty analysis, (3) TRISTAN for three-dimensional radiation transport calculation and (4) MEDUSA-IB for one-dimensional hydrodynamic calculation of the implosion and thermonuclear burn of an ion beam driven ICF target.
Technical issues and requirements of experiments and facilities for fusion nuclear technology