论文部分内容阅读
在低压低干度汽水两相流稳定性实验研究的基础上 ,建立了对 2 0 0MW核供热堆热工水力学实验回路HRTL 2 0 0进行分析计算的均相模型。稳态流动特性和密度波振荡特性的分析结果表明 :均相模型获得的稳态流量分析结果大于实验值 ;均相模型虽能得到高干度和低干度两个密度波振荡区域 ,但在低干度区域 ,不考虑过冷沸腾区时 ,均相模型给出的结果不能清楚显示出原本很狭窄的低含汽量流动不稳定区域及两条稳定边界
Based on the experimental research on the stability of low-pressure and low-dryness two-phase flow, a homogeneous model was established for the analysis and calculation of HRTL20 0 in the thermomechanical experimental loop of 200 MW nuclear heating reactor. The results of steady-state flow and density wave oscillation show that the steady-state flow rate obtained by the homogeneous model is larger than the experimental value. Although the homogeneous model can obtain two density wave oscillation regions with high dryness and low dryness, In the low-dryness region, when the subcooling boiling region is not considered, the results given by the homogeneous model can not clearly show the originally narrow and unstable region with low vapor content and two stable boundaries