Upward two-phase flow in two different vertical narrow gaps was investigated
experimentally. For better understanding the characteristics of air-water flow in rectangular …

In order to predict the thermal–hydraulic parameters in nuclear reactor accurately, it is
essential to reveal the phase distribution characteristics, the mechanisms of phase …

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 …

The phase distribution in rod bundle channel was associated with the heat transfer
coefficient, flow resistance and critical heat flux, which was of great significance for the …

An evaluation methodology of a thermal-hydraulics based on a mechanism in light water
reactors (LWRs) is needed from a viewpoint of the safety analysis during normal operation …

Drift-flux model has been one of the most popular models predicting two phase flow
parameters in nuclear reactor and other industrial equipment since proposed. Most of …

In order to simulate the transfer of mass, momentum and energy in the gas-liquid two-phase
flow system, tremendous work focused on the phenomenon, mechanisms and models for …

Aiming at understanding the phase distribution characteristics and developing the transition
criterion from wall-peak to core-peak phase distribution in a rod bundle channel, air–water …

Critical heat flux (CHF) is the most important parameter related to the safety performance of
heat exchanging equipment, whose triggering mechanisms are very complex and …

To improve the understanding on the mechanisms of phase distribution and bubble
interaction for cap bubbly flow in rod bundles, the adiabatic upward cap bubbly flow has …