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 …

In order to investigate two-phase bubbly flow through fuel assembly of pressurized water
reactor (PWR), the wire mesh sensor (WMS) is employed to measure air-water flow in a up …

Interfacial transfer terms in gas-liquid two-phase flows are formulated as the product of
interfacial area concentration (IAC) and flux. The interfacial area transport equation (IATE) is …

Tight lattice fuel assemblies have significant advantages in power density and conversion
ratios. However, the dynamic characteristics of two-phase flow in tight lattice bundles, which …

Two-phase flows in rod bundles or tube bundles appear in heat transfer systems. The
bundle-average (or one-dimensional) void fraction is a critical parameter in overall system …

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 …

In this study, a numerical model of two-phase flow boiling in a rod bundle channel was
developed to investigate the influence of spacer grid's arrangement on thermal-hydraulic …

Mixing vane grids (MVGs) are an integral part of nuclear reactor fuel assembly, and
significantly impact the flow and heat transfer characteristics of the coolant in a rod bundle …

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 …