In severe accident conditions with loss of active cooling in the core, zirconium alloys, used
as fuel cladding materials for current light water reactors (LWR), undergo a rapid oxidation …

Thermal hydraulic analysis of nuclear reactor core and its associated systems can be
performed using analysis system, subchannel or computational fluid dynamics (CFD) codes …

In this study, we experimentally investigate the flow field characteristics in a fuel rod bundle
with a spacer grid and split-type mixing vanes at a low Reynolds number of 14, 000. Time …

In this study, we experimentally investigated the flow field characteristics in the complex
geometry of a tightly packed 61-rod bundle with wire spacers by employing matched-index …

The purpose of the present study is to present new hydraulic benchmark data obtained for
PWR rod bundles for the purpose of benchmarking computational fluid dynamics (CFD) …

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 …

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 …

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 …