ANTEO (from the Italian words: ANalisi TErmoidraulica Ottimizzata – optimised thermal-hydraulic analysis) is a sub-channel code for steady state thermal hydraulic analysis of nuclear reactor fuel bundles. The code was developed by Silvio Cevolani in ENEA in 1992. Given the general growing interest in lead, the need emerged in ENEA to have a code for LFRs thermal-hydraulic calculations, therefore ANTEO was upgraded to meet this challenge. Correlations for the physical properties of the reactor materials used in LFR were introduced. The Rehme method for the pressure drop calculation, specifically developed for rod bundles in LMFBR (Liquid Metal Fast Breeder Reactors), was implemented. Two recent models for turbulent mixing, suitable for use with liquid metals were introduced. The formula recommended by Mikityuk was inserted, as an alternative correlation for Nu calculation. ANTEO-LFR was successfully applied in the core analysis of the demonstrative LFR, ALFRED; the results will be presented in a separate report.

ANTEO-LFR: a pc code for thermal-hydraulic optimized core analysis in a Lead Fast Reactor

Mattioli, Davide
2012-12-12

Abstract

ANTEO (from the Italian words: ANalisi TErmoidraulica Ottimizzata – optimised thermal-hydraulic analysis) is a sub-channel code for steady state thermal hydraulic analysis of nuclear reactor fuel bundles. The code was developed by Silvio Cevolani in ENEA in 1992. Given the general growing interest in lead, the need emerged in ENEA to have a code for LFRs thermal-hydraulic calculations, therefore ANTEO was upgraded to meet this challenge. Correlations for the physical properties of the reactor materials used in LFR were introduced. The Rehme method for the pressure drop calculation, specifically developed for rod bundles in LMFBR (Liquid Metal Fast Breeder Reactors), was implemented. Two recent models for turbulent mixing, suitable for use with liquid metals were introduced. The formula recommended by Mikityuk was inserted, as an alternative correlation for Nu calculation. ANTEO-LFR was successfully applied in the core analysis of the demonstrative LFR, ALFRED; the results will be presented in a separate report.
Rapporto tecnico;Termoidraulica del nocciolo;Reattori nucleari veloci;Generation IV reactors
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/7498
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