Measurement of Air/Water Co-Current Flow in a Large Slab

A multi-dimensional two-phase flow characteristic is very important for safety of a nuclear reactor. Most conventional safety analysis codes could not predict proper dynamic features for such a flow condition since those are based on a one-dimensional flow geometry. A lot of effort to improve the capability of safety analysis codes has been made in respect to system or component-wise frames. To develop and validate an analysis code, a sufficient experiment database representing the multi-dimensional two-phase flow is required under well-defined boundary conditions. In this study, an air-water test is performed in a rectangular- shaped test section which has a large cross-section. The measured data includes global and local parameters. Local two-phase parameters such as a void fraction and liquid/air velocities are measured by local conductivity probes and BDFTs (Bi-Directional Flow Tube)