Thermal Conductivity of UO2 Fuel: Predicting Fuel Performance from Simulation

被引：15
作者：
Phillpot, Simon R. [1 ]
El-Azab, Anter [2 ,3 ]
Chernatynskiy, Aleksandr [1 ]
Tulenko, James S. [1 ,4 ]
机构：
[1] Univ Florida, Dept Mat Sci & Engn, Gainesville, FL 32611 USA
[2] Florida State Univ, Dept Computat Sci, Tallahassee, FL 32310 USA
[3] Florida State Univ, Mat Sci Program, Tallahassee, FL 32310 USA
[4] Univ Florida, Nucl Engn Program, Gainesville, FL 32611 USA
来源：
JOM | 2011年 / 63卷 / 08期
关键词：
HIGH BURNUP; URANIUM-DIOXIDE; LATTICE WAVES; RIM STRUCTURE; TRANSPORT; SCATTERING; RESISTANCE;
D O I：
10.1007/s11837-011-0143-x
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
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.
引用
收藏
页码：77 / 83
页数：7
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