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 …

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 …

The thermal-hydraulic performance of nuclear fuel has a very important effect on the safety
and economy of a reactor. The helical cruciform fuel (HCF) is an innovative fuel design with …

Experimental study of coherent structures downstream of a spacer grid with different
inclination angles (20°, 25°, 30°) of split-type mixing vanes in a 5× 5 rod bundle was …

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 …

To investigate the effect of fuel assembly bowing on coolant flow and heat transfer, three-
dimensional thermal–hydraulic characteristics of 5× 5 bowing fuel assembly are investigated …

Pressurized water reactors (PWRs) are the most common types of electricity generating
nuclear reactors. Within their cores, fuel rods generate heat by fission and the high-pressure …

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 …

Axial and lateral pressure loss in a 5× 5 rod–bundle with a split-type mixing vane spacer grid
was experimentally measured using differential pressure transmitters at different sub …