LAUSR

Abstract Flow oscillation of two-phase flow has significant effect on the safety of relative industrial application, such as nuclear reactor. Oscillation of mass flux can induce undesirable such as boiling crisis. In this paper, a visual experimental study is carried out in a single rod channel to investigate the mechanism of flow oscillations. The system pressure is from 0.1 MPa to 1.0 MPa with different mass flux and inlet subcooling. According to the characteristics of the flow oscillation combined with bubble behavior, the flow oscillation is divided into slightly flow oscillation with high subcooled and high mass flux condition, boiling onset flow oscillation with bubbly flow and flow patterns transition oscillation with flow pattern transition. In this paper, the effect of thermal conditions on flow oscillation is also analyzed and discussed in detail.