Thermophysical properties of inert matrix fuels for actinide transmutation
Source abstract
Abstract
Abstract 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.
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Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Thermodynamic and Structural Properties of Metals and Alloys
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References (21)
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