The QUENCH-11 experiment conducted at FZK-Karlsruhe has been analyzed with ICARE/CATHARE V1 and V2 far code validation purposes. This experiment, aimed at investigating care heatup and degradation during boil-off and successive quenching, was the reference test far a code benchmark exercise in the frame of SARNET European project. In the V2 version of ICARE/CATHARE the test bundle thermal hydraulics is dealt with by the CATHARE2 code. The V2 code version results have been compared with the results of a stand-alone ICARE2 V3 Mod2.0 calculation representative of the use of ICARE/CA THARE V1, in which the test bundle thermal-hydraulics is calculated by ICARE2. The results of both calculations have been compared with the experimental data in order to verify the capability of these codes to simulate severe accident situations in nuclear reactors.

Post-Test Analysis of QUENCH-11 Experiment with ICARE/CATHARE Code

Bandini, G.
2007

Abstract

The QUENCH-11 experiment conducted at FZK-Karlsruhe has been analyzed with ICARE/CATHARE V1 and V2 far code validation purposes. This experiment, aimed at investigating care heatup and degradation during boil-off and successive quenching, was the reference test far a code benchmark exercise in the frame of SARNET European project. In the V2 version of ICARE/CATHARE the test bundle thermal hydraulics is dealt with by the CATHARE2 code. The V2 code version results have been compared with the results of a stand-alone ICARE2 V3 Mod2.0 calculation representative of the use of ICARE/CA THARE V1, in which the test bundle thermal-hydraulics is calculated by ICARE2. The results of both calculations have been compared with the experimental data in order to verify the capability of these codes to simulate severe accident situations in nuclear reactors.
Rapporto tecnico;Reattori nucleari ad acqua;Sicurezza nucleare;Analisi incidentale
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/5256
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