超临界二氧化碳临界流理论研究  

Theoretical Study of Supercritical Carbon Dioxide Critical Flow

作　　者：汪杨乐 周源 刘秀婷 黄彦平[1] 王俊峰[1] 

机构地区：[1]中国核动力研究设计院,四川 成都 [2]四川大学物理学院,四川 成都

出　　处：《核科学与技术》2021年第3期138-146,共9页Nuclear Science and Technology

摘　　要：反应堆动力循环系统破口事故研究是反应堆安全分析的重要组成部分。针对伴随的临界流现象,建立了均相热平衡模型(HEM)和均相松弛模型(HRM)进行分析。计算发现,两个模型均能较好地计算超临界二氧化碳的临界流的质量流量,最大误差不超过16.1%。其中,HEM模型的平均误差为5.5%,HRM模型的最低平均误差为3.9% (ϴ = 10−5)。HRM模型具有更好的计算精度。同时,计算还得到了不同参数下出口含气率变化特性与管内物性参数变化过程。对相变延迟现象对超临界二氧化碳临界流流动的影响进行了更加深入的分析,为破口事故安全分析提供理论支持和参考。The leakage accident in reactor power system is an important problem in safety analysis. To analyze Critical Flow phenomenon in accidents better, a Homogeneous Equilibrium Model (HEM) and a Ho-mogeneous Relaxation Model (HRM) were established. After calculation, both models can accurately calculation mass flow rate of supercritical carbon dioxide. The maximum error is less than 16.1%. The average error of HEM model is 5.5%. The minimum error of HRM model is 3.9% (ϴ = 10−5). The HRM model has higher accuracy. At the same time, the mass vapor ratio at outlet and parameter changing process in the test section are also obtained. The effect of phase transition delay of super-critical carbon dioxide critical flow has further analyzed and it provides more reference for the nu-clear safety analysis.

关 键 词：超临界二氧化碳 临界流 核安全 

分 类 号：TM6[电气工程—电力系统及自动化]