A comparative assessment of different empirical equations for single-phase heat transfer in rod bundles of a lead (or LBE) cooled fasi reactor has been carried out. The work has focused on the effect of the Peclet number and pitch of an hexagonal or square lattice fuel assembly, essentially with clean coolant and metal surface. The effect of Pb oxides on heat transfer has not been analyzed. The analysis doesn't claim to be exhaustive.

Comparative Assessment of Empirical Correlations for Single-Phase Heat Transfer in Rod Bundles of HLM Cooled Reactors

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2007-04-27

Abstract

A comparative assessment of different empirical equations for single-phase heat transfer in rod bundles of a lead (or LBE) cooled fasi reactor has been carried out. The work has focused on the effect of the Peclet number and pitch of an hexagonal or square lattice fuel assembly, essentially with clean coolant and metal surface. The effect of Pb oxides on heat transfer has not been analyzed. The analysis doesn't claim to be exhaustive.
Rapporto tecnico;Generation IV reactors;Reattori nucleari veloci;Termoidraulica dei reattori nucleari
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/5301
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