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Transactions of the Japan Society of Mechanical Engineers Series B
Multi-physics analysis system for a heat transfer tube failure event in a steam generator of sodium-cooled fast reactors has been developed. The analysis system consists of the multiple computer codes. In this study, applicability of the newly constructed numerical models in the analysis system was investigated. The droplet entrainment / transport model which was incorporated into the SERAPHIM code was verified through the analysis of the related experiment. The experimental data about thedoi:10.1299/kikaib.79.2635 fatcat:fy24q6vpnbco5p6xvnxt2tb4ji