MODELING OF GAS-PHASE TRANSPORT IN HEAVY LIQUID-METAL COOLANT FLOW IN THE HYDRA-IBRAE/LM THERMOHYDRAULIC CODE

摘要

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.