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以假想核动力装置为研究对象，计算了双恒定运行方式下主冷却剂系统的流动阻力特性，在此基础，提出了主泵变频调速曲线，并对堆芯热通道的流动不稳定性进行了分析
Taking the hypothetical nuclear power plant as the research object, the flow resistance characteristic of the main coolant system under dual constant operation mode was calculated. Based on this, the main pump frequency conversion speed regulation curve was proposed and the flow instability of the core thermal passageway Analysis