Thermal Conductivity of UO₂ Fuel: Predicting Fuel Performance from Simulation

Author

Simon R. Phillpot
Anter A. El-Azab
Aleksandr V. Chernatynskiy, Missouri University of Science and TechnologyFollow
James S. Tulenko

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.

Recommended Citation

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, The Minerals, Metals & Materials Society (TMS), Aug 2011.

The definitive version is available at https://doi.org/10.1007/s11837-011-0143-x

Department(s)

Physics

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)

1047-4838

Document Type

Article - Journal

Document Version

Citation

File Type

text

Language(s)

English

Rights

© 2011 The Minerals, Metals & Materials Society (TMS), All rights reserved.

Publication Date

01 Aug 2011