Thermal-hydraulic analysis of two-phase flow plays a crucial role in the optimal design of
nuclear fuel assemblies and in nuclear safety. This paper presents the state of the art in two …

The interfacial area transport equation (IATE) is employed to describe the evolution of
interfacial structure and evaluate the interfacial area concentration of two-phase flow …

A tight lattice rod (or tube) bundle is a promising design concept to enhance heat transfer
efficiency in heat exchangers using a phase change. Understanding gas-liquid two-phase …

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 …

Flow regime identification based on local parameters of axial upward two-phase flow in
vertical tube bundles, at high-temperature and high-pressure, was performed using optical …

This paper investigated the two-phase flow characteristics in a double sub-channel tight
lattice (P/D= 1.06). Compared to the prototype, the test channel was magnified by 2.7 times …

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 …

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 …

The spacer grid has a significant impact on the thermal-hydraulic characteristics of the rod
bundle channel, which directly determines the possibility of a boiling crisis. The multi-phase …

To investigate the transitional criterion of bubbly to slug flow influenced by gap size in
rectangular channels, an experimental investigation of air-water two-phase co-current …