In this paper, the thermal fluid-dynamics results of the DHR pre-test calculation performed using the FLUENT commercial CFD code and the preliminary comparison with the experimental data obtained in the first set of experiments are reported. The CIRCE pool facility has been refurbished to host a suitable test section able to thermal-hydraulically simulate the primary system of a HLM cooled pool reactor. A single pipe of DHR bayonet-tubes was installed in the ICE test section, to study decay heat removal from the core of a LFR in the case of an accidental event with total loss of the secondary circuit and consequent reactor scram. In order to better represent the boundary conditions, a one way coupled model between the RELAP5 system code and the CFD Fluent code was used. Pre-test simulations predict a well defined region with thermal stratification at the exit of the DHR. Moreover, after 20 hours of transient the DHR inside the ICE test section is able to remove about 39 kW of thermal power, which represents 5% of the nominal power, thanks to thermal stratification phenomena that in this condition is foreseen inside the downcomer region of the ICE test-section. A preliminary experimental test confirmed the presence of this thermal stratification region inside the liquid metal pool.

Thermal-Hydraulic Analysis of the DHR System of ELFR with the ICE Test Section

FORGIONE, NICOLA;MARTELLI, DANIELE;
2013-01-01

Abstract

In this paper, the thermal fluid-dynamics results of the DHR pre-test calculation performed using the FLUENT commercial CFD code and the preliminary comparison with the experimental data obtained in the first set of experiments are reported. The CIRCE pool facility has been refurbished to host a suitable test section able to thermal-hydraulically simulate the primary system of a HLM cooled pool reactor. A single pipe of DHR bayonet-tubes was installed in the ICE test section, to study decay heat removal from the core of a LFR in the case of an accidental event with total loss of the secondary circuit and consequent reactor scram. In order to better represent the boundary conditions, a one way coupled model between the RELAP5 system code and the CFD Fluent code was used. Pre-test simulations predict a well defined region with thermal stratification at the exit of the DHR. Moreover, after 20 hours of transient the DHR inside the ICE test section is able to remove about 39 kW of thermal power, which represents 5% of the nominal power, thanks to thermal stratification phenomena that in this condition is foreseen inside the downcomer region of the ICE test-section. A preliminary experimental test confirmed the presence of this thermal stratification region inside the liquid metal pool.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/426467
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