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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Thermal conductivity calculation of ZrC-ZrO2 pellet from powder metallurgy as the surrogate of UCO kernel fuel
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Thermal conductivity calculation of ZrC-ZrO2 pellet from powder metallurgy as the surrogate of UCO kernel fuel

机译：粉末冶金ZrC-ZrO2颗粒作为UCO内核燃料代理的热导电性计算

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摘要

The very high-temperature reactor is one of the conceptual generation IV reactor design, which is an advanced type of high-temperature reactor concept with enhanced safety and increased helium coolant outlet temperature for process heat of the industrial field. This reactor employed UCO (UO2-UCx) fuel kernel providing resistance against fuel kernel migration and internal pressure buildup. Recently, only a few reported literature about the thermal conductivity calculation of UCO fuel. The UO2 has phonon contribution domination, while UC has electrical contribution domination to the thermal conductivity. This combination behavior is important to be studied by measurement and calculation of thermal conductivity. The present work deals with the estimation of thermal conductivity considering the contacting particle inside the pellet. The ZrC-ZrO2 pellet was used as the surrogate of UCO composite. The calculation of thermal conductivity was performed by the Agari model and percolation theory showed a good agreement to the experimental value. (C) 2020 The Authors. Published by Elsevier B.V.
机译：非常高温的反应器是概念发电IV反应器设计之一，是一种高温反应器概念的先进类型，具有增强的安全性和工业领域工艺热量的氦气冷却剂出口温度。该反应器采用UCO（UO2-UCX）燃料核，从而为燃料核迁移和内部压力累积提供抵抗力。最近，只有少数报道关于UCO燃料的导热性计算的文献。 UO2有声子贡献统治，而UC对导热系数具有电气贡献统治。这种组合行为对于通过导热率的测量和计算来研究是重要的。本工作涉及考虑颗粒内部接触颗粒的导热率的估计。 ZrC-ZrO2颗粒用作UCO复合材料的替代物。通过Agari模型和渗滤理论进行导热率的计算表现出对实验值的良好一致性。 （c）2020作者。由elsevier b.v出版。

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