基于FLUENT的多物理场耦合研究

基于FLUENT的多物理场耦合分析是当前核安全分析的热点问题。本文运用6组缓发中子的点堆动力学模型（PKM）编写了反应堆核功率计算程序，利用外部调用耦合和用户自定义函数（UDF）动态链接库耦合方法分别建立了FLUENT-REALP5耦合分析模型和FLUENT-PKM耦合分析模型，并在单相范围内利用水平分支管道的喷放问题和线性反应性引入的超功率瞬变问题验证了耦合模型的正确性和有效性。本研究的耦合分析方法可以为FLUENT的多物理场核安全分析提供支撑。 

Research on Multi-Physics Coupling Based on FLUENT

Multi-physics coupling analysis based on FLUENT is a hot issue in current nuclear safety analysis. The reactor nuclear power calculation program (PKM) was prepared by using the point reactor neutron kinetic equations of 6 groups of delayed neutrons. The FLUENT/RELAP coupling analysis model and the FLUENT/PKM coupling analysis model were established by the external coupling method and secondary development coupling method respectively. The correctness and effectiveness of the coupled model were verified by the discharge problem of the horizontal branch pipe and the super-power transient problem of the linear reactivity introduced in a single-phase range. The coupled analysis method of the study can provide support for fluent multi-physics nuclear safety analysis.