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Modeling and Measurement of Thermal Properties of Ceramic Composite Fuel for Light Water Reactors

机译：轻水堆陶瓷复合燃料热性能的建模与测量

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摘要

The thermal modeling of a composite fuel consisting of continuous second phase in a ceramic (uranium oxide) matrix has been carried out with aid of detailed examination of the microstructure of the composite and the interface structure. BeO and SiC were considered as second phase dispersed in UO2 matrix by weight from 0-15% to enhance the thermal conductivity. It is found that with 10% SiC, the thermal conductivity increases from 5.8 to 9.8 Wlm-K at 500 K. A finite element analysis computer program AN SYS was used to create composite fuel geometries with set boundary conditions to produce accurate thermal conductivity predictions. The results were compared to analytical calculations as previously performed with the series geometry to verify the validity of using ANSYS in producing accurate thermally enhanced nuclear fuel models. Good agreement was found between experimental measured thermal conductivity for BeO-UO2 matrix and the model predictions.
机译：在详细检查复合材料的微观结构和界面结构的基础上，对由陶瓷（氧化铀）基质中的连续第二相组成的复合燃料进行了热建模。 BeO和SiC被认为是第二相，以0-15％的重量比分散在UO2基质中，以提高导热性。发现使用10％的SiC，在500 K时热导率从5.8 Wlm-K增加。使用有限元分析计算机程序AN SYS创建具有设定边界条件的复合燃料几何形状，以产生准确的热导率预测。将结果与以前使用系列几何进行的分析计算进行比较，以验证使用ANSYS生成精确的热增强核燃料模型的有效性。在实验测量的BeO-UO2基质的热导率与模型预测之间找到了很好的一致性。

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