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Research on Neutron Diffusion and Thermal Hydraulics Coupling Calculation based on FLUENT and its Application Analysis on Fast Reactors

机译:基于FLUENT的中子扩散与热工水力耦合计算研究及其在快堆中的应用分析

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摘要

In this study, based on the UDF and UDS function of the FLUENT, the neutron diffusion equation is defined. There is no requirement to develop the interface program of the coupling calculation. Then the assembly is fine modeled and the solver in the FLUENT is used to solve the neutron diffusion equation. The thermal-hydraulics calculation is carried out at the same time. Therefore the coupling calculation between neutron diffusion and thermal-hydraulics is achieved on the same solver of the FLUENT. In order to achieve the convenient data transfer, the neutron diffusion and thermal-hydraulics calculation use the same meshes.
机译:在这项研究中,基于FLUENT的UDF和UDS函数,定义了中子扩散方程。不需要开发耦合计算的接口程序。然后对装配进行精细建模,并使用FLUENT中的求解器求解中子扩散方程。热工液压计算同时进行。因此,在相同的FLUENT求解器上可以实现中子扩散与热工液压件之间的耦合计算。为了实现方便的数据传输,中子扩散和热工水力计算使用相同的网格。

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