Gas-liquid two-phase flows are utilized in various heat and mass transfer processes that
appear in numerous industrial apparatus. Typical examples are chemical reactors, heat …

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 …

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 …

During pressurized water reactor (PWR) operations, the two-phase flow may occur in local
subchannels, such as the reactivity-insertion accident. The gas phase will migrate laterally to …

During operation of a nuclear power plant, the bending deformation of fuel rods usually
occurs and has a substantial effect on the heat transfer and flow behavior of coolant. To …

In order to improve the ability to predict nuclear reactor behaviour, reliable measurement of
the void fraction in a subchannel is essential. A subchannel impedance void meter (SCIVM) …

针对新型定位格架夹持结构及其疲劳问题, 利用有限元分析手段评估其运行条件下的应力状态,
并开展弹簧疲劳特性实验, 分析疲劳失效特性及裂纹萌生位置. 结果表明, 该夹持结构的弹簧疲劳 …

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 …