Abstract
Two-phase flow is an important and common phenomenon in reactor systems, and there are significant differences in the heat and mass transfer characteristics of two-phase flow under different flow patterns. Researchers have proposed a variety of flow pattern transition mechanisms to predict the two-phase flow. But limited by the means of measurement, the critical void fraction for flow pattern transition can’t be determined. Two types of bubbly-slug flow transition criteria in vertical circular tubes are studied in this paper and a wire mesh sensor (WMS) was manufactured to measure the critical void fraction for bubbly-slug transition. 147 visualization tests were carried out for validation.
Highlights
In nuclear reactor system, two-phase flow is a common and important phenomenon
For the adiabatic air water two phase flow in vertical circular tubes, the most widely used bubbly-slug flow transition criteria were proposed by Mishima and Ishii (1984) and Taitel et al (1980)
Mishima-Ishii bubbly-slug flow transition mechanism is based on the drift flow model, and the superficial velocity of the two phases given by Equation (1)
Summary
Two-phase flow is a common and important phenomenon. The structure of gas liquid interface is very complex because of the interaction between the phases and it varies as the velocity changes of the two phases. The authors of the present paper manufactured a WMS to measure the critical void fraction for bubbly-slug flow transition. For the adiabatic air water two phase flow in vertical circular tubes, the most widely used bubbly-slug flow transition criteria were proposed by Mishima and Ishii (1984) and Taitel et al (1980). Mishima-Ishii bubbly-slug flow transition mechanism is based on the drift flow model, and the superficial velocity of the two phases given by Equation (1). The bubble velocity isn’t studied in this paper, so just one effective two layers WMS is applied to measure the void fraction.
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