Simulation Research on Flow Instability of Parallel Multi-channel System Based on Modelica
In the parallel channel of the nuclear reactor core,flow instability can lead to a significant decrease in critical heat flux(CHF)or mechanical oscillation of the core fuel assembly,thereby endangering the normal operation of the reactor.In order to solve this problem,based on a high-temperature and high-pressure steam water two-phase thermal hydraulic experimental device,a parallel dual channel system model was built using NUMAP software for flow instability simulation research.The experiment shows that when the number of parallel channels is 2,3,and 4,the flow instability boundary of the parallel multi-channel system under the same operating conditions is calculated through simula-tion,and the calculation error of the flow instability boundary is not more than±5%.It is verified that the flow instability boundary can be ob-tained by using a parallel dual channel structure when there are multiple parallel heating channels,and the transient analysis ability of the soft-ware for flow instability phenomena is confirmed.
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NSTL
万方数据
维普
