反应堆压力容器下降段水-蒸汽CCFL实验与模型研究

陈登高, 毕景良, 黄彦平, 袁德文, 昝元锋, 徐建军

陈登高, 毕景良, 黄彦平, 袁德文, 昝元锋, 徐建军. 反应堆压力容器下降段水-蒸汽CCFL实验与模型研究[J]. 原子能科学技术, 2022, 56(6): 1034-1044. DOI: 10.7538/yzk.2021.youxian.0950
引用本文: 陈登高, 毕景良, 黄彦平, 袁德文, 昝元锋, 徐建军. 反应堆压力容器下降段水-蒸汽CCFL实验与模型研究[J]. 原子能科学技术, 2022, 56(6): 1034-1044. DOI: 10.7538/yzk.2021.youxian.0950
CHEN Denggao, BI Jingliang, HUANG Yanping, YUAN Dewen, ZAN Yuanfeng, XU Jianjun. Experimental and Modeling Investigation on Steam-water CCFL Phenomena in Reactor Downcomer[J]. Atomic Energy Science and Technology, 2022, 56(6): 1034-1044. DOI: 10.7538/yzk.2021.youxian.0950
Citation: CHEN Denggao, BI Jingliang, HUANG Yanping, YUAN Dewen, ZAN Yuanfeng, XU Jianjun. Experimental and Modeling Investigation on Steam-water CCFL Phenomena in Reactor Downcomer[J]. Atomic Energy Science and Technology, 2022, 56(6): 1034-1044. DOI: 10.7538/yzk.2021.youxian.0950

反应堆压力容器下降段水-蒸汽CCFL实验与模型研究

Experimental and Modeling Investigation on Steam-water CCFL Phenomena in Reactor Downcomer

  • 摘要: 为探究反应堆压力容器下降段在喷放末期冷段安注过程中的水-蒸汽逆流特性,建立下降段逆向流动限制(CCFL)模型,开展了基于压力容器模化本体的下降段CCFL实验研究以及建模分析。通过实验研究获得了不同入口安注水流量、安注水过冷度、堆芯蒸汽流量等条件下的下降段环腔内的安注特性数据,并基于实验数据进行了CCFL建模分析。结果表明,开始发生CCFL的蒸汽无量纲流速与入口安注水无量纲流速呈现正相关,基于无量纲流速建立的模型斜率与入口安注水无量纲流速呈现高度指数关联。本文建立了适用于从不发生CCFL至不完全CCFL,再到完全CCFL的下降段水-蒸汽气液逆流全过程预测模型。

     

    Abstract: Experimental test study was conducted on modeled reactor pressure vessel to investigate the steam-water counter-current flow limitation (CCFL) characteristics in the reactor downcomer during emergency core coolant (ECC) injection through the cold leg. In this study, the reactor pressure vessel of a PWR was scaled by 1∶5.8 using modified linear scaling method. The scaling focuses on the downcomer whose geometry is the same with the actual reactor. The core was simulated by steam generating tubes. ECC was injected through two cold legs and flowed out through a break in another cold leg. The mass flow rate of the inlet ECC, generated steam, penetrated water into the lower vessel, and bypass water and steam was measured. The inlet ECC flow rate was also scaled from actual reactor. ECC experiment data were obtained under different inlet ECC flow rates, subcooling degrees and core steam flow rates. During the experiment, the vessel pressure maintains between 0.2 MPa·abs and 0.6 MPa·abs, and the core steam temperature is within 10 ℃ superheat. Under each test run, the inlet ECC mass flow rate is unchanged, the core steam mass flow rate ranges from small to large corresponding to ECC total penetration to near zero penetration. The experiment results show that the steam condensation fraction increases with inlet water mass flow rate and decreases with core steam mass flow rate. The penetration water dimensionless velocity has a highly linear negative relation with the steam dimensionless velocity after onset of CCFL. CCFL model of Wallis and Kutateladze type was derived from the obtained experiment data. The effect of condensation on the steam flow rate in the downcomer was calculated through an empirical equation. Results show that the CCFL model trend for each inlet ECC mass flow rate is similar. Wallis and Kutateladze type model is capable for every inlet ECC mass flow rate. CCFL model parameter derived from dimensionless velocity has a highly exponential relation with the normalized inlet ECC velocity. In this way, the relations of steam dimensionless velocity and penetrated ECC dimensionless velocity under different inlet ECC mass flow rates could be calculated using one model. The analysis result shows that the mean uncertainties of Wallis and Kutateladze models are about 8.10% and 9.02% in this study.

     

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  • 刊出日期:  2022-06-19

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