Drift-flux parameter modeling of vertical downward gas–liquid two-phase flows for interfacial drag force formulation
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DOI: 10.1016/j.nucengdes.2021.111185
Abstract: Abstract The two-fluid model has been adopted as a platform of nuclear thermal–hydraulic system analysis code because it can treat the mechanical and thermal non-equilibrium between phases through the interfacial transfer terms. Precise modeling of… read more here.
Keywords: two phase; drag force; interfacial drag; drift flux ... See more keywords