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Numerical investigation of rod bundle thermal–hydraulic behavior during reflood transients using COBRA-TF

Yue Jin, F. B. Cheung, Koroush Shirvan, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie

2020Annals of Nuclear Energy25 citationsDOI

Topics & Concepts

BundleNuclear engineeringThermal hydraulicsSubcoolingHeat transferEnvironmental scienceCoolantHeaderMass flow rateMechanicsMaterials scienceComputer scienceMechanical engineeringEngineeringPhysicsComposite materialComputer networkNuclear reactor physics and engineeringNuclear Engineering Thermal-HydraulicsHeat transfer and supercritical fluids
Numerical investigation of rod bundle thermal–hydraulic behavior during reflood transients using COBRA-TF | Litcius