Thermal Transport in Actinide Oxide Fuels With Interstitial Defects

Katherine Mitchell, H. Horner, A. Resnick, Jungkyu Park, E. Farfán, T. Yee, A. Hummel
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Abstract

Molecular displacement occurs in the oxide fuels of nuclear reactors during operation. This causes several types of point defects to be generated inside the oxide nuclear fuels. To improve the safety and efficiency of nuclear reactor operation, it is necessary to better understand the effects of point defects on the properties of the oxide fuels. In this study, we examine the effects of interstitial defects on thermal transport in two representative actinide oxides used in modern reactors (UO2, and PuO2). Reverse non-equilibrium molecular dynamics (RNEMD) is employed to approximate the thermal conductivities for the aforementioned fuels at several sample lengths and at defect concentrations of 0.1%, 1%, and 5%. The results show that alterations to the lattice structures of these fuels reduce their thermal conductivities significantly. For example, oxygen interstitial defects at concentrations even as low as 0.1% decreased thermal conductivity by 20% at 100 units for each fuel.
含间隙缺陷的锕系氧化物燃料的热输运
核反应堆的氧化物燃料在运行过程中会发生分子位移。这导致在氧化物核燃料内部产生几种类型的点缺陷。为了提高核反应堆运行的安全性和效率,有必要更好地了解点缺陷对氧化物燃料性能的影响。在这项研究中,我们研究了在现代反应器中使用的两种具有代表性的锕系氧化物(UO2和PuO2)中,间隙缺陷对热输运的影响。采用反向非平衡分子动力学(RNEMD)来近似上述燃料在不同样品长度和缺陷浓度为0.1%、1%和5%时的导热系数。结果表明,这些燃料的晶格结构的改变显著降低了它们的导热系数。例如,即使氧浓度低至0.1%,每种燃料100单位时,氧间隙缺陷也会使导热系数降低20%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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