Nuclear Technology · 1994 · 11 citations · 6 references
EngineeringDesign AspectsLiquid Metal CoolingEnergy EfficiencyReactor DesignMechanical EngineeringNuclear Reactor DesignGas-liquid FlowEngineering ThermodynamicsScaled Loop GeometrySystems EngineeringThermodynamicsThermal ModelingVoid DriftMultiphase FlowHeat TransferHeat ExchangerThermal ManagementThermal EquilibriumThermal Engineering
In order to study the thermohydraulic behavior of a natural-circulation-cooled boiling water reactor (BWR) fuel assembly, such as void drift, flow pattern distribution, and stability, a scaled loop geometry is designed.For modeling the steam/water flow in a BWR fuel assembly, scaling criteria are derived using the onedimensional drift-flux model. Thermal equilibrium and subcooled boiling conditions are treated separately, resulting in one overall set of criteria. Scaling on all flow regimes that can be present in a normal fuel assembly leads to fixing both the assembly mass flux and the geometric dimensions. When Freon-12 is used as a modeling fluid, model assembly dimensions must be 0.46 of the prototype. Total power consumption must be reduced by a factor 50.To sustain cooling by natural circulation, a modeled chimney and downcomer are included.
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G. C. Pomraning · Nuclear Science and Engineering · 1976 · 315 citations
Two-Phase Flow and Heat Transfer
W.L. Kirchner · Nuclear Science and Engineering · 1978 · 162 citations