Drift-flux parameter modeling of vertical downward gas-liquid two-phase flows for interfacial drag force formulation

Dong, CS; Hibiki, T

Hibiki, T (corresponding author), Purdue Univ, Sch Nucl Engn, 400 Cent Dr, W Lafayette, IN 47907 USA.

NUCLEAR ENGINEERING AND DESIGN, 2021; 378 ():

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 n......

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