Concepedia

Subchannel flow and enthalpy distributions at the exit of a typical nuclear fuel core geometry

Frank S. Castellana, J.E. Casterline

Nuclear Engineering and Design · 1972 · 64 citations · 4 references

Concepts

EngineeringNuclear EngineeringPhysicsHeat TransferNuclear PhysicsThermodynamicsAnnular FlowHeat Transfer In ReactorsReactor Core DesignReactor DesignReactor KineticsThermal-hydraulic Safety AnalysisCore Thermal-hydraulic DesignCore Thermal-hydraulic ResponseEnthalpyMixing EnthalpyReactor Core ModelingReactor Core PhysicsThree-dimensional Core Modeling

References

4

Prediction of pressure drop during forced circulation boiling of water

J. R. S. Thom · International Journal of Heat and Mass Transfer · 1964 · 584 citations

Engineering, Mechanical Engineering, Physics +12

Forced convection subcooled boiling—prediction of vapor volumetric fraction

S. Lévy · International Journal of Heat and Mass Transfer · 1967 · 448 citations

Engineering, Mechanical Engineering, Physics +11

Mass Flux and Enthalpy Distribution in a Rod Bundle for Single- and Two-Phase Flow Conditions

R.T. Lahey, B.S. Shiralkar, D. W. Radcliffe · Journal of Heat Transfer · 1971 · 51 citations

Engineering, Mechanical Engineering, Fluid Dynamics +10

COOLANT INTERCHANNEL MIXING IN REACTOR FUEL ROD BUNDLES: SINGLE-PHASE COOLANTS.

J. T. Rogers, N.E. Todreas · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1969 · 33 citations

Engineering, Chemical Engineering, Nuclear Engineering +9