Out-of-pile thermo physical properties and chemical compatibility of 'Pu' based fuels

Thermo physical properties and out-of-pile chemical compatibility of nuclear fuels are of great technical importance to reactor fuel designer. The technology of nuclear reactors could be improved through better computer code which needs accurate material property data. The design margin can be minimised with accuracy of the input data which in turn improves the economy. In the present investigation some of the important thermo physical properties like thermal conductivity/diffusivity, thermal expansion coefficient, heat capacity, solidus temperature, high temperature hardness of Pu based fuel eg. mixed uranium plutonium carbide/nitride/oxide fuels for fast reactor and (Th, Pu) O₂ fuel for thermal reactor have been presented