子通道程序与CFD程序的耦合方法研究

随着多种新型堆型的发展，堆芯设计将更加紧凑，为了保证堆芯安全，要求在设计阶段尽可能地精确计算出堆芯内热工参数分布，这就需要针对特定瞬态工况开展堆芯多尺度耦合研究。本文在已有的子通道程序COBRA-EN的基础上，采用动态链接库技术将其耦合到流体动力学程序FLUENT中，开发了适用于堆芯多尺度计算的COBRA-EN/FLUENT耦合程序。进一步通过带腔室的棒束通道算例，分别测试了稳态和瞬态情况下耦合程序的计算精度，结果显示COBRA-EN与FLUENT两者的耦合是有效且可靠的。本研究成果将为新型堆芯的设计和安全分析提供可靠的工具。

Coupling Method between Subchannel Code and CFD Code

With the development of many new types of reactors, the core design will be more compact. In order to ensure the safety of the reactor core, it is required to calculate the distribution of thermal parameters in the reactor core as accurately as possible during the design phase, which requires core multi-scale coupling research for specific transient state conditions. Based on the existing subchannel code COBRA-EN, the dynamic link library technology was used to couple it into the fluid dynamics code FLUENT, and the COBRA-EN/FLUENT coupling code suitable for core multi-scale calculation was developed in this paper. Further, through some examples of rod bundle channel with a chamber, the calculation accuracy of the coupling code under steady state and transient state conditions was tested respectively. The results show that the coupling between COBRA-EN and FLUENT is effective and reliable. The results of this study will provide reliable tools for the design and safety analysis of new cores.