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 ...
Computational fluid dynamic investigations of flow through an aged CANDU pressure tube
Single-phase, isothermal computational fluid dynamics simulations of twelve simplified CANDUTM 37M fuel bundles sitting in both as-received and aged pressure tubes were performed with Hydra in this work. The predicted ...