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 …

Nuclear safety demonstration is a key issue where thermal hydraulics plays a central role,
whether at the design stage or for nuclear power plants lifetime extension. Combined with …

Reflooding experiments with rod bundles at Loss Of Coolant Accident (LOCA) conditions
usually use intrusive methods with limited access and, consequently, their data are not …

During a loss of coolant accident (LOCA), blocked sub-channels may appear due to the
swelling of the fuel rods' cladding, which results in flow redistribution during the reflooding …

IRSN has developed DRACCAR code in order to model loss of coolant accidents (LOCA) in
a light water nuclear reactor. The physics during a hypothetical loss of coolant accident …

Les écoulements et les transferts de masse et de chaleur en leur sein sont des sujets
d'intérêt pour de nombreuses situations accidentelles des études de sûreté des réacteurs …

A loss-of-coolant accident (LOCA) in a Pressurized Water Reactor (PWR) can occur
because of a breach in the primary circuit, leading to a sudden pressure drop and …

During a loss of coolant accident (LOCA), in a nuclear-pressurized water reactor, fuel
assemblies can heat up and water is injected to cool down the core. In this hypothetical …

Liquid thermometry is always challenging as one intends to perform the measurements as
little invasive as possible. Since the use of physical sensors like thermocouples can disturb …

Many processes in thermal engineering involve droplets impacting on heated surfaces: in
metallurgy, where spray cooling is used to produce steel plates and bars; in nuclear …