This document aims to survey the studies widely conducted on the heat transfer models and pressure drops evaluation to be used in T/H system codes for the safety assessment of Liquid Metal Reactors, in particular devoted to wire-wrapped rod bundles (SFR-like). An overview of a wide set of empirical correlations for single-phase heat transfer in tubes and rod bundles for heavy liquid metal is given as well as the most extensively accepted methods to estimate the pressure drops on wire-wrapped rod bundle configurations, collecting the most valuable literature in these fields, without the claim to be exhaustive. Finally, the main heat transfer and pressure drop correlations are tested against a SFR-like rod bundle to verify their performances in predicting the thermal exchange between the clad and sodium coolant, and the pressure drops through the core in hexagonal wire-wrapped configuration. The results here obtained aim to improve the consistency of the simulations conducted with the system codes.

Review of heat transfer and pressure drop correlations for liquid metal in T/H system codes

Bandini, Giacomino;Polidori, Massimiliano
2016-01-28

Abstract

This document aims to survey the studies widely conducted on the heat transfer models and pressure drops evaluation to be used in T/H system codes for the safety assessment of Liquid Metal Reactors, in particular devoted to wire-wrapped rod bundles (SFR-like). An overview of a wide set of empirical correlations for single-phase heat transfer in tubes and rod bundles for heavy liquid metal is given as well as the most extensively accepted methods to estimate the pressure drops on wire-wrapped rod bundle configurations, collecting the most valuable literature in these fields, without the claim to be exhaustive. Finally, the main heat transfer and pressure drop correlations are tested against a SFR-like rod bundle to verify their performances in predicting the thermal exchange between the clad and sodium coolant, and the pressure drops through the core in hexagonal wire-wrapped configuration. The results here obtained aim to improve the consistency of the simulations conducted with the system codes.
Rapporto tecnico;Trasmissione del calore;Generation IV reactors;Analisi di sicurezza
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/7878
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