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Thermal conductivity of fabricated UO$2$Mo pellet

Fig. $8$ shows the thermal conductivity as function of temperature for UO$210$ vol$\%$ Mo pellet and pure UO$2$ pellet. The calculated thermal conductivities adjusted to $95\%$TD utilising the relationship proposed by Brandt and Neuer $[21].$

The thermal conductivities for each material followed the typical trend observed for UO$2,$ gradual degradation with increasing temperature. The thermal conductivity of the different composites was found to increase with the concentration of Mo$.$ The comparative increase was most significant at the higher temperatures measured. For example, the thermal conductivity at $800\backslash$deg C was increased by about $62\%$ for pellets with non$-$pre$-$sintered granules and UO$2$ granules pre$-$sintered at $800\backslash$deg C and about $36\%$ for pellet with UO$2$ granules pre$-$sintered at $1200\backslash$deg C$.$ It has been shown that the thermal conductivity of pellets containing no pre$-$sintered and UO$2$ granules pre$-$sintered at $800\backslash$deg C are more effectively enhanced, due to the relatively intact microstructure. While the non$-$homogeneous distribution of molybdenum and increased porosity in pellets containing pre$-$sintered uranium dioxide grains at $1200\backslash$deg C showed a significant effect on thermal conductivity as expected. It is inevitable that a uranium loading decrease due to the Mo addition in UO$2$ pellet. However, it is expected that the loss of uranium loading amounts can be compensated through the enhanced performance of micro$-$cell pellets. In the case of metallic micro$-$cell pellet, owing to an enhanced fuel temperature margin, a reactor power can be safely uprated. Then, the loss can be compensated by an enhanced fuel economy. It can be also compensated by the optimization of design parameters such as pellet density and pellet diameter Nevertheless, the decreased fuel cycle length and the increased neutron absorption by Mo addition must be indispensably considered $[20,21].$ Using the developed fabrication technology of metallic micro$-$cell pellet, it can be made an attempt to apply other candidates for cell wall materials with lower neutron absorption cross section. In addition, it is necessary to minimize the amounts of cell wall material addition through the optimization of fabrication technology and parameters.