Litcius/Paper detail

Flow boiling experiments for CHF evaluation under downward-facing heating including flow visualization: Effects of pressure, orientation, mass flux, and local quality

Jun Yeong Jung, Min Suk Lee, Hae Min Park, Yong Hoon Jeong

2022Annals of Nuclear Energy21 citationsDOI

Topics & Concepts

Critical heat fluxMass fluxMaterials scienceMechanicsBoilingFlow (mathematics)Parametric statisticsOrientation (vector space)Flow visualizationVapor qualityHeat fluxVisualizationLimit (mathematics)Flow conditionsFlux (metallurgy)Nuclear engineeringThermodynamicsHeat transferMechanical engineeringPhysicsMathematicsGeometryStatisticsEngineeringMathematical analysisMetallurgyNuclear Engineering Thermal-HydraulicsHeat Transfer and Boiling StudiesNuclear Materials and Properties