Thermal Conductivity of UO2 Fuel: Predicting Fuel Performance from Simulation
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.
S. R. Phillpot et al., "Thermal Conductivity of UO2 Fuel: Predicting Fuel Performance from Simulation," JOM Journal of the Minerals, Metals and Materials Society, vol. 63, no. 8, pp. 73-79, Minerals, Metals and Materials Society (TMS), Aug 2011.
The definitive version is available at https://doi.org/10.1007/s11837-011-0143-x
Keywords and Phrases
Atomic levels; Experimental database; Fuel performance; Integrated programs; Materials model; Mesoscale simulation; Recent progress; Thermal Performance; Computer simulation; Fuels; Nuclear reactors; Transport properties; Thermal conductivity
International Standard Serial Number (ISSN)
Article - Journal
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