Prediction of critical heat flux (CHF) in annular flow is important for the safety of once - through steam generator and the reactor core under accident conditions. The dryout in annular flow occurs at the point where the film is depleted due to entrainment, deposition, and evaporation. The film thickness, film mass flow rate along axial distribution, and CHF are calculated in vertical upward round tube on the basis of a separated flow model of annular flow. The theoretical CHF values are higher than those derived from experimental data, with error being within 30%.
Fan, P., Qiu, S. Z., & Jia, D. N. (2006). An investigation of flow characteristics and critical heat flux in vertical upward round tube. Nuclear Science and Techniques/Hewuli, 17(3), 170–176. https://doi.org/10.1016/S1001-8042(06)60033-X