Nuclear Technology · 1977 · 20 citations · 4 references
EngineeringMaterials ScienceNuclear EngineeringHeat TransferNuclear ChemistryNuclear MaterialsFuel CharacteristicsFuel ChemistryHigh-level Radioactive WasteNuclear FissionNuclear Fuel ChemistryNuclear Fuel MaterialsCarbide FuelCarbide-based MaterialsFission ReactionsHigh-burnup Fuel BehaviorPlutonium Oxide FuelRare-earth OxidesThermal ConductivityThermal Conductivity Of Nuclear Fuel
Carbide-based fuels simulating high burnup were prepared by addition of inactive fission product elements. They contained fission product phases of the UMoC2 and U2RUC2 type, and a rare-earth oxide phase. The thermal conductivity of the material is within the range observed for carbide-based fuels free of fission products. The diffusion of plutonium was considerably enhanced by the addition of fission products. The solid fission product swelling rate of a carbide-based fuel was estimated to be 0.5% per at.% burnup.
4