A three-dimensional numerical study on steady state was designed for a safety relief valve
using several openings and inlet pressures. The ANSYS-CFX® commercial code was used …

The development of modern computational fluid dynamics (CFD) technology provides many
preliminary references for experimental design. In addition, the CFD calculation results …

In order to achieve high-fidelity PIV measurement for cross flow in rod bundles, the
measurement approach with the two-dimensional (2D) PIV has been optimized …

In reactor fuel assembly in PWR, spacer grids with mixing vanes are used in rod bundles to
enhance flow mixing and heat transfer. Thus, the spacer grids have significant influence on …

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 examined the capabilities and limitations of steady Reynolds-Averaged Navier–
Stokes (RANS) approach for pressurized water reactor (PWR) rod bundle problems, based …

In spite of the low fuel failure rate in currently operating water cooled nuclear power reactors,
operations are increasingly demanding with higher burn-up, power increases, cycle lengths …

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 …

A new test facility is presented, enabling single-phase isothermal fluid mechanics
experiments to support nuclear reactor safety studies. The applied measurement technique …

In nuclear power industry, the energy conservation of heat exchangers is a crucial demand.
The current study addresses the influence of nano-encapsulated phase change material …