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 …

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 …

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 …

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 …

This paper presents the experimental results and analyses of the friction and local pressure
loss coefficient of a 5× 5 rod bundle with spacer grid. Based on the experimental data …

Approximate turbulence energy dissipation time-scaling for the subsonic steam–water two-
phase flows has been investigated using a dedicated experimental facility. Steam and water …

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 …

Computational advancements in the past couple of decades have propelled the capabilities
to design, model, and benchmark nuclear reactor systems. However, the lack of high …

The author would like to express sincere gratitude to his supervisor Prof. Toshihiro
Yamamoto for giving him the invaluable opportunity to come to Kyoto University to perform …