Title

Thermal Conductivity of UO2 Fuel: Predicting Fuel Performance from Simulation

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.

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 Minerals, Metals and Materials Society (TMS), All rights reserved.

Share

 
COinS