Accurate prediction of critical heat flux (CHF) is important for enhancing the reliability and
efficiency of systems used in the energy and power engineering sectors. Traditional physical …

In the current study, based on a small-scale quench test facility, the two-phase flow interface
behavior during quench transients is visualized and analyzed utilizing an image processing …

Accurate simulation of reflood transients of a reactor core is one of the top priorities for
nuclear reactor thermal–hydraulic and safety analysis. An in-depth understanding of the two …

In this paper, we present an approach to inversely quantify the uncertainty of MCFD
simulations through a data-driven modular Bayesian inference. Both the model parameter …

When the water inventory evaporates during a hypothetical loss of coolant accident in the
core of a pressurized water reactor, the fuel rods temperature increases substantially …

Accurate prediction of the reflood transients during LOCA has long been a challenging task.
One reason for this is the substantial cost incurred to perform large-scale reflood tests, which …

Plate-type fuel assembly is employed in the miniaturized nuclear reactor and submarine,
and it is essential to investigate the flow and heat transfer during reflooding for safety …

This study aims to explore the dynamic distribution and hydrodynamic characteristics of
droplets during the highly transient process of reflood. However, the quasi-steady state …

Abstract During a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor, partial
or complete drying of fuel assemblies may take place. In these conditions, the fuel …

The reflood process after a loss of coolant accident (LOCA) in a nuclear reactor involves
complex two-phase flow with low pressure and flow rate, as well as boiling phase transition …