Thermal hydraulic characteristics of spiral cross rod bundles in a lead–bismuth-cooled fast reactor
Yue Zeng, Pingjian Ming, Feng‐Chen Li, Hong-Na Zhang
Topics & Concepts
Materials scienceSpiral (railway)MechanicsCoolantCross section (physics)Heat transferReynolds numberFlow (mathematics)Thermal hydraulicsHeat fluxHeat exchangerHydraulic diameterThermodynamicsMechanical engineeringPhysicsTurbulenceQuantum mechanicsEngineeringNuclear reactor physics and engineeringNuclear Engineering Thermal-HydraulicsHeat transfer and supercritical fluids