Abstract
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.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
