Abstract
Recent progress in understanding the thermal-transport properties of UO2 for fission reactors is reviewed from the perspective of computer simulations. A path to incorporating more accurate materials models into fuel performance codes is outlined. In particular, it is argued that a judiciously integrated program of atomic-level simulations and mesoscale simulations offers the possibility of both better predicting the thermal-transport properties of UO2 in light-water reactors and enabling the assessment of the thermal performances of novel fuel systems for which extensive experimental databases are not available.
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Phillpot, S.R., El-Azab, A., Chernatynskiy, A. et al. Thermal conductivity of UO2 fuel: Predicting fuel performance from simulation. JOM 63, 73–79 (2011). https://doi.org/10.1007/s11837-011-0143-x
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DOI: https://doi.org/10.1007/s11837-011-0143-x