Wettability and CHF limits of Accident-Tolerant nuclear fuel cladding materials in light water reactor conditions
Guosheng Su, Tiago Augusto Moreira, Daesu Lee, A.K. Jena, G. Wang, A. Byers, Bren Phillips, Zeses Karoutas, Mark Anderson, Matteo Bucci
Topics & Concepts
Materials scienceZirconium alloyWettingCladding (metalworking)ChromiumCritical heat fluxMetallurgyCoatingBoilingComposite materialZirconiumHeat fluxHeat transferThermodynamicsPhysicsNuclear Materials and PropertiesNuclear Engineering Thermal-HydraulicsHeat transfer and supercritical fluids