Thermo-physical properties of dispersion nuclear fuel for a new-generation reactors: A computational approach

Tomsk Polytechnic University is conducting a series of experiments to develop a nuclear fuel manufacturing technology required for a new-generation innovative nuclear systems. In this study, the thermal conductivity and thermophysical properties were calculated for the proposed nuclear fuel, which are necessary before proceeding to the construction stage. The cylindrical fuel compact consisting of spherical coated constituents (Pu,Th)O2 of BISO type, were sintered together within a graphite matrix (C). Also, a composite material made of nuclear fuel (Pu,Th)O2 and refractory oxides BeO/MgO, were prepared using plasma-chemical synthesis method. The development of a fuel pellet with desired physical properties that can be exposed for a long time under irradiation in a high-temperature gas-cooled thorium reactor core is the main technological advantage of the present study.Tomsk Polytechnic University is conducting a series of experiments to develop a nuclear fuel manufacturing technology required for a new-generation innovative nuclear systems. In this study, the thermal conductivity and thermophysical properties were calculated for the proposed nuclear fuel, which are necessary before proceeding to the construction stage. The cylindrical fuel compact consisting of spherical coated constituents (Pu,Th)O2 of BISO type, were sintered together within a graphite matrix (C). Also, a composite material made of nuclear fuel (Pu,Th)O2 and refractory oxides BeO/MgO, were prepared using plasma-chemical synthesis method. The development of a fuel pellet with desired physical properties that can be exposed for a long time under irradiation in a high-temperature gas-cooled thorium reactor core is the main technological advantage of the present study.