收稿日期: 2008-05-08
修回日期: 2008-11-05
网络出版日期: 2009-05-15
基金资助
中国科学院研究生院院长基金资助
Experiment and numerical simulation of thermal conductivity of uranium dioxide
Received date: 2008-05-08
Revised date: 2008-11-05
Online published: 2009-05-15
王增辉 , 黄潇凤 . 二氧化铀热导率的实验及数值模拟研究评价[J]. 中国科学院大学学报, 2009 , 26(3) : 415 -418 . DOI: 10.7523/j.issn.2095-6134.2009.3.017
Uranium dioxide is a kind of steady nuclear fuel that has the characteristic of high melting point and steady property. The thermal conductivity of uranium dioxide can directly influence the temperature distribution of nuclear fuel and the max temperature of the center of nuclear fuel. The experimental results and expression of thermal conductivity have been compared in the paper. The deviation between the experiment results has decreased. The non-equilibrium molecular dynamics simulation results are in good agreement with the experiment results in medium temperature region. In low temperature region, it is necessary to add the quantum correction to the kinetic energy computation of phonon. In high temperature region, it is needed to use the accurate potential model and build up the electron gas energy transport model and photon radiation energy transport to study the thermal conductivity well and truly for the nuclear reactor safety design and uranium dioxide engineering application.
Key words： uranium dioxide; thermal conductivity; molecular dynamics
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