Turbulent Flow of Coolant in an Advanced Recycling Nuclear Reactor
Cross-Channel Flow in a Nuclear Reactor
Interchannel cross-flow is the principal cross-assembly energy transport mechanism for sodium fast reactors. For this design, uniformity temperatures enable peak power output. This Nek5000 simulation modeled the coolant for a 217 pin reactor, using an unstructured mesh with over one billion degrees of freedom per time slice. The visualization, done with VisIt, aimed to better understand the flow distribution, which is required for improving future designs.
Hank Childs and colleagues from Lawrence Berkeley Laboratory, 2009