Researchers & students at the Thermal Hydraulic Laboratory of the Center of Nuclear Technology Development (CDTN) have performed studies on single phase flows such as the thermally stratified flows, flows in ducts with obstructions (perforated plates, nozzles or grids), flows through rod bundles, and also two-phase flows as stratified countercurrent flow. These studies relate to nuclear systems safety. Experiments performed at the Laboratory are simulated numerically using ANSYS Academic CFX software, resulting in the final monographs of Engineering and Graduated students in the field of CFD. Below are some images from simulations carried out at the Laboratory:
Flow through nozzle/perforated plate
Thermal stratified flow
Flow through rod bundle