In view of an important role of a one-dimensional drift-flux correlation in nuclear thermal-
hydraulic system analysis codes, several drift-flux correlations such as Lellouche–Zolotar …

This paper has studied the flow regimes and their transitions in upward gas-liquid two-phase
flows in vertical rod bundle flow channels. The past experimental observations on the flow …

During operation of the nuclear power plant, fuel rods tend to bend. In order to accurately
predict the thermal-hydraulic phenomena in the rod bundles with bowing rod, the profile of …

In this paper, the wire-mesh sensor (WMS) has been successfully introduced into a typical
pressurized water reactor (PWR) prototype 5× 5 rod bundle channel. Combined with the …

A new drift-flux correlation has been developed to predict void fraction over a wide range of
two-phase flow conditions in rod bundle geometries. An experimental database that …

An experiment has been performed to measure void fraction at stagnant to low liquid flow
conditions in a rod bundle. An 8× 8 rod bundle test facility scaled from a boiling water reactor …

In this paper we evaluated a single plane ultrasonic tomography sensor and performed
some experimentation to reconstruct three-dimensional profiles in a chemical bubble …

This study has reviewed the past research for adiabatic and boiling GLTP (gas-liquid two-
phase) flows in VNR (vertical narrow rectangular) flow channels. 1758 void fraction …

This paper has reviewed 17 available drift-flux correlations and collected 959 existing void
fraction experimental data for air-water and steam-water two-phase flows in the vertical rod …

In this article, two fluid conservation equations of gas–liquid two-phase transient flows are
deduced with an improved mass transfer model between two phases and applied to liquid …