Thermophysical properties of inert matrix fuels for actinide transmutation

The thermal transport properties of a set of ‘inert matrix fuels’ (IMFs) for actinide transmutation were investigated and compared. Heat capacity, thermal diffusivity and conductivity were measured in the usable temperature range for MgO- and ZrO2-based IMFs containing uranium, plutonium and americium, and sintered from co-precipitated or blended oxide powders.