首页|Evaluation of thermophysical properties of UO2-10 Vol% Mo nuclear fuel pellets
Evaluation of thermophysical properties of UO2-10 Vol% Mo nuclear fuel pellets
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NSTL
Elsevier
Uranium dioxide (UO 2 ) -molybdenum (Mo) composites have been proposed as accident tolerant fuel candidates due to their high thermal conductivity, high melting point, high boiling point, and ability to have low thermal neutron absorption cross-section. It is therefore essential to evaluate the method of fabrication and thermophysical properties of this system. In this work, UO 2 -Mo samples with a Mo fraction of 10 Vol% and different densities were fabricated using spark plasma sintering (SPS). This method allows sintering at relatively low temperatures and within a short time. Experimental analysis was performed on UO 2 -Mo specimens to characterize thermal diffusivity and thermal conductivity as a function of temperature up to 900 degrees C. Thermophysical properties were analyzed for various densities, and grain sizes as a function of temperature. The grain size and microstructural differences related to porosity were also analyzed using the scanning electron microscopic (SEM) and electron backscatter diffraction (EBSD). (c) 2021 Elsevier B.V. All rights reserved.
NSTL
Elsevier
