Void-fraction distribution under high-pressure boil-off conditions in rod bundle geometry

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	Year	Citations
Proposed Correlation of Data for Isothermal Two-Phase, Two-Component Flow in Pipes R.W. Lockhart Chemical engineering progress EngineeringHeat ExchangerFluid MechanicsPipe FlowMechanical Engineering	1949	2.7K
The Thermal-Hydraulics of a Boiling Water Nuclear Reactor P.A. Lottes Nuclear Science and Engineering Core Thermal HydraulicsEngineeringPhysicsThermal HydraulicsReactor Design	1978	210
Full-range drift-flux correlation for vertical flows B. Chexal, G.S. Lellouche OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) EngineeringFluid MechanicsGas-liquid FlowDrift-flux ParametersGeophysical Flow	1985	74
Void fraction under high pressure, low flow conditions in rod bundle geometry T.M. Anklam, R.F. Miller Nuclear Engineering and Design Low Flow ConditionsCompressible FlowEngineeringPhysicsMechanics	1983	61
Experiments and void correlation for PWR small-break LOCA conditions J.P. Cunningham, Hsu‐Chieh Yeh Transactions of the American Nuclear Society	1973	31
Full-range drift-flux correlation for vertical flows. Revision 1 B. Chexal, G.S. Lellouche GeophysicsFull-range Drift-flux CorrelationEnvironmental Fluid DynamicEngineeringFluid Mechanics	1986	15

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