Approaches to modeling gas-phase transport in heavy liquid-metal coolant flow in the HYDRA-IBRAE/LM code, which is actual for safety validation of nuclear reactors with a leak in the steam-generator tubes, are examined. A hierarchy of models for determining the dispersed-particle size that are implemented in the code for bubble flow is presented: empirical correlation, transport equation for the density of the interfacial surface area, and kinetic equation for the particle-size distribution function. The results of test calculations are presented.
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Translated from Atomnaya Énergiya, Vol. 129, No. 3, pp. 134–141, September, 2020.
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Alipchenkov, V.M., Grudtsyn, Y.V. & Mosunova, N.A. Modeling of Gas-Phase Transport in Heavy Liquid-Metal Coolant Flow in the HYDRA-IBRAE/LM Thermohydraulic Code. At Energy 129, 127–134 (2021). https://doi.org/10.1007/s10512-021-00723-w
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DOI: https://doi.org/10.1007/s10512-021-00723-w