Selected results of three Direct Numerical Simulations are presented, on relevant test cases for the thermal hydraulics of liquid metal-cooled nuclear reactors, encompassing a wide spectrum of turbulent convection regimes. The first test case is a Rayleigh-Benard cell at a moderately high Grashof number, representative of the conditions in the unstably stratified layer of fluid in a reactor pool. The second case is the mixed convection in a cold-hot-cold triple jet configuration, representative of the mixing liquid streams exiting from the core into the pool, and relevant for the modeling of thermal striping and thermal fatigue phenomena on the vessel containment walls. The third case is the fully-developed flow in a vertical bare rod bundle with triangular arrangement and a large pitch-to-diameter ratio, in both forced and mixed convection conditions, representative of normal operation or decay heat removal flow conditions in the reactor core, respectively. The availability of these numerical databases will allow for an in-depth analysis of the turbulent flow and heat transfer in liquid metals under different convection regimes, and is also relevant for the development, calibration and validation of turbulent heat transfer models.

DIRECT NUMERICAL SIMULATION OF NATURAL, MIXED AND FORCED CONVECTION IN LIQUID METALS: SELECTED RESULTS / Fregni, A.; Angeli, D.; Cimarelli, A.; Stalio, E.. - (2020), pp. 349-362. (Intervento presentato al convegno 2020 International Topical Meeting on Advances in Thermal Hydraulics, ATH 2020 tenutosi a na nel 2020).

DIRECT NUMERICAL SIMULATION OF NATURAL, MIXED AND FORCED CONVECTION IN LIQUID METALS: SELECTED RESULTS

Fregni A.;Angeli D.;Cimarelli A.;Stalio E.
2020

Abstract

Selected results of three Direct Numerical Simulations are presented, on relevant test cases for the thermal hydraulics of liquid metal-cooled nuclear reactors, encompassing a wide spectrum of turbulent convection regimes. The first test case is a Rayleigh-Benard cell at a moderately high Grashof number, representative of the conditions in the unstably stratified layer of fluid in a reactor pool. The second case is the mixed convection in a cold-hot-cold triple jet configuration, representative of the mixing liquid streams exiting from the core into the pool, and relevant for the modeling of thermal striping and thermal fatigue phenomena on the vessel containment walls. The third case is the fully-developed flow in a vertical bare rod bundle with triangular arrangement and a large pitch-to-diameter ratio, in both forced and mixed convection conditions, representative of normal operation or decay heat removal flow conditions in the reactor core, respectively. The availability of these numerical databases will allow for an in-depth analysis of the turbulent flow and heat transfer in liquid metals under different convection regimes, and is also relevant for the development, calibration and validation of turbulent heat transfer models.
2020
2020 International Topical Meeting on Advances in Thermal Hydraulics, ATH 2020
na
2020
349
362
Fregni, A.; Angeli, D.; Cimarelli, A.; Stalio, E.
DIRECT NUMERICAL SIMULATION OF NATURAL, MIXED AND FORCED CONVECTION IN LIQUID METALS: SELECTED RESULTS / Fregni, A.; Angeli, D.; Cimarelli, A.; Stalio, E.. - (2020), pp. 349-362. (Intervento presentato al convegno 2020 International Topical Meeting on Advances in Thermal Hydraulics, ATH 2020 tenutosi a na nel 2020).
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11380/1315466
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