Now showing items 1-3 of 3
Assessment of FLUENT CFD code as an analysis tool for SCW applications
Chosen as one of six Generation‒IV nuclear-reactor concepts, SuperCritical Water-cooled Reactors (SCWRs) are expected to have high thermal efficiencies within the range of 45 ‒ 50% owing to the reactor‟s high pressures and ...
A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes
Wall thinning of carbon steel in CANDU reactor outlet feeder pipes due to Flow Accelerated Corrosion (FAC) is identified as one of the challenges for CANDU reactors since it would force them to shut down due to safety ...
CFD determination of fluid and geometry related localized heat transfer phenomena for supercritical water flow
The proposed concept of Supercritical Water-cooled Reactor (SCWR) as part of the Generation IV International Forum aims to improve the thermal efficiency over current power plants by utilizing cooling water at pressures ...