γ射线法测量高压管束间气液两相流的截面含气率分布

在立式蒸汽发生器垂直管束间的气液两相流中,截面含气率是其中一个重要参数。使用γ射线法对高温高压下垂直管束间气液两相流截面含气率的分布规律进行了实验研究。实验压力分别为5、7、9 MPa,质量流速为300 kg/(m²?s),热力学干度的范围为0.003 ~ 0.4。实验得到了垂直管束间截面含气率随热力学干度、体积含气率和压力的变化关系;并与经典公式的计算结果对比发现,在低干度区域,实验结果与Miropolskii模型、Smith模型和Armand模型偏差较大,均大于30%,在高干度区域偏差较小;基于Armand理论,通过多元线性回归法拟合出本文工况下平均截面含气率的计算关联式,与日本核动力工程公司(NUPEC)的实验数据偏差小于15%。本研究对蒸汽发生器的结构设计和流动特性研究具有重要意义。

Void fraction distribution of vapor-water two-phase flow in vertical tube bundles using gamma densitometer

In the vapor-water two-phase flow between vertical tube bundles of steam generators, void fraction is an important parameter. Gamma ray method was used to measure the void fraction distribution under high temperature and high pressure. The experimental pressures were 5, 7, 9 MPa, respectively,the mass flow was 300 kg/(m²?s), and the thermodynamic vapor quality ranged from 0.003 to 0.4. The distribution of the void fraction in vertical tube bundles was obtained and the effects of thermodynamic vapor quality and volume fraction were investigated. Compared with the classical formula calculation model, in the low-dry zone, the relative error between Miropolskii model, Smith model and Armand model with the experimental data are more than 30%, in areas with high dryness, error is small. Based on Armand model, a practical correlation of average void fraction and volume fraction on the section was calculated by multiple linear regression. It can be concluded that the correlations agree well with Japan Nuclear Power Engineering Corporation (NUPEC) experimental data, the relative error is less than 15%. The results show that a gamma ray method can be used to measure and predict the distribution of the void fraction in vertical tube bundles under high-temperature and high-pressure effectively. In general, it is of great significance to the structural design and flow characteristics of steam generator.