Antonello Palazzi
EngD student
Sponsor(s)
Research project
Nuclear thermal hydraulic analysis using coupled CFD and nuclear system codes
Nuclear thermal hydraulic analysis using coupled CFD and nuclear system codes
The thermal hydraulic analysis of nuclear reactors is performed by 1D System Codes. These codes predict the flows in the complex network of the elements that together form the thermal hydraulic systems of a nuclear reactor. Modern CFD is able to produce high-quality predictions of flows in complex geometries, but only with the use of large computing resources. Thus, much of the primary circuit may be modelled with adequate fidelity using a cheap 1D system code, and it may only be in a limited part of the circuit that full 3D modelling is important.
Contact information
Email: a.palazzi12@imperial.ac.uk