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Multiscale Investigation of Thermal Transport in UO_2 Fuel using Modeling and Simulation

机译:UO_2燃料热传递的多尺度建模与仿真研究

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摘要

The thermal conductivity of LWR fuel is one of the most critical material parameters impacting the efficiency and safety of the reactor. Thus, a significant effort is being made to develop a mechanistic understanding of the impact of temperature and burnup on it. In this work, we have provided a short summary of modeling and simulation efforts being carried out at the atomistic and mesoscale to understand this critical property. These research efforts are providing a fundamental understanding of the thermal transport in unirradiated UO_2, as well as the impact of radiation damage and fission products on thermal transport. These efforts have been focused on UO_2, but they also are laying the framework for conducted similar simulations to investigate new accident tolerant fuel concepts.
机译:轻水堆燃料的热导率是影响反应堆效率和安全性的最关键的材料参数之一。因此,人们正在作出巨大的努力来发展对温度和燃尽影响的机械理解。在这项工作中,我们提供了在原子尺度和中尺度进行的建模和仿真工作的简短摘要,以了解这一关键特性。这些研究工作提供了对未经辐照的UO_2中的热输运以及辐射破坏和裂变产物对热输运的影响的基本理解。这些工作集中在UO_2上,但它们也为进行类似的模拟奠定了基础,以研究新的可容忍事故的燃料概念。

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