Abstract
The article is devoted to the new and improved models, implemented in system thermohydraulic HYDRA-IBRAE/LM code, being developed in IBRAE RAN, which make it possible to carry out more realistic simulation of thermohydraulic parameters in case of a steam generator tube rupture in reactor plant with lead coolant: a model to estimate initial bubble diameter, a model of steam-water mixture behavior in liquid lead and interfacial area transport equation to define the evolution of the dispersed phase size.The paper also contains the models validation results on experiments conducted in Kutateladze Institute of Thermophysics Siberian Branch of the Russian Academy of Sciences (IT SB RAN). The experimental researches were devoted to the study of the initial bubble size dependence on the gas flow rate and the heat exchange between steam-water mixture and liquid lead. The comparison of calculation results and experimental data demonstrates not only qualitative but also good quantitative agreement.
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