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 …

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 …

The current research aims at investigating the thermal–hydraulic non-equilibrium
encountered in the dispersed flow film boiling (DFFB) regime under reflood conditions. A …

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 …

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 …

Reflooding is a complicated thermal-hydraulic process in a loss of coolant accident (LOCA)
related to the nuclear reactor safety issues. Due to the physical nature of multi-scale behind …

Abstract The US Nuclear Regulatory Commission has been conducting thermal-hydraulic
research using the Rod Bundle Heat Transfer (RBHT) facility at the Pennsylvania State …

Water droplets are generated in the reflood period of a large break loss-of-coolant accident
by either shattering of liquid ligament or interfacial shear force. As generated droplets …

Much effort has been devoted by the nuclear community to develop mechanistic models to
predict the heat dissipation of fuel rods during a loss of coolant accident (LOCA). However …

The prediction of the drop size distribution (DSD) resulting from liquid atomization is key to
the optimization of multiphase flows from gas-turbine propulsion through agriculture to …