In nuclear fuel assembly mixing vanes are fabricated on the spacer grids to promote
diversion cross flow and turbulent mixing. In order to investigate the decay of diversion cross …

The thermal–hydraulic analysis of coolant flow in the reactor core plays a significant role in
the optimized design of nuclear fuel assemblies and nuclear safety. This article reviews the …

Cross flow and lateral pressure drop downstream a split-type mixing vane spacer grid in a
5× 5 rod bundle were experimentally measured by particle image velocimetry (PIV) and …

This study summarizes experimental investigations of the flow field characteristics in the
cross-flow planes of a 5× 5 rod bundle with spacer grid and split-type mixing vanes. Under …

As a valid numerical method to obtain a high-resolution result of a flow field, computational
fluid dynamics (CFD) have been widely used to study coolant flow and heat transfer …

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 …

In this paper, the time-resolved particle image velocimetry (TR-PIV) and match index
refractive (MIR) techniques were used to study the flow field in a large range (0–22 D h) …

The crossflow is the key phenomenon in turbulent flow inside rod bundles. In order to
establish confidence on application of computational fluid dynamics (CFD) to simulate the …

The coolant flow behavior inside fuel bundles influences the subchannel mass and
momentum exchange and the cladding temperature, which should be considered when …

The turbulent flow in a fuel bundle affects the heat transfer from the fuel rods to the coolant,
which is a concerned issue in the design of fuel assemblies. In this paper, an experiment …