Study on Local Sub-Cooling Boiling in the Vertical Upward Pipe

In the heat transfer pipes of nuclear reactors with complex mass and heat exchange, there exists phenomenon of local sub-cooling boiling. Based on the Eulerian two-fluid model, this paper studied the local sub-cooling boiling phenomenon in the vertical upward pipe at a pressure of 4.5MPa. Firstly, a closed sub-cooling boiling model was built to make comparison with the existing experimental results of Bartolomei, the result of which is in great agreement with the experimental data. What’s more, the parameters of the experimental working conditions were expanded, it helped to analyze data that could not be directly measured in the experiment. The physical mechanism behind data distribution law mainly included the influence of the wall bubble departure diameter, the wall bubble departure frequency, and nucleation density. It is found that the RPI model has a good predictive ability for the liquid temperature field. The nucleation density model corresponding to KI combined with the wall departure diameter model KI can well predict the distribution of the void fractions in the pipe. Finally, the influence on heat and mass transfer of heating power along the pipe was analyzed. This paper put forward suggestions for the modification of the sub-cooling boiling model to help it predict the distribution of bubbles in the main flow region more precise.