The assessment of numerical tools for the Safety Analysis of GFR and the demonstrator ALLEGRO is the objective of the GoFastR Task 1.5.3. The available experimental data related to the HEFUS3 (ENEA Brasimone, Italy) integraI facility cooled by helium are considered with reference to the 2009 experimental campaign. Seven organizations (ENEA, PSI, AEKI/CEA, KIT, NRG, RC-Rez) are involved in the benchmark exercise with six different codes (RELAP5, TRACE, CATHARE, SIM-GFR, SPECTRA and FLUENT). The capabilities of this wide spread of transient analysis codes to describe the T/H behavior of a helium system is verified both in steady-state and transient conditions (LOFA). On the basis of a code-to-code benchmark and code-to-experiment comparison, the present document summarizes the exercise outcomes, providing the descriptions of the code models as well as the main calculation results. Taking into account the limits of the HEFUS3 experimental data, the analysis of the results has led to a generaI positive evaluation of the codes performance, allowing to draw some recommendations on gas cooled systems modeling and the needs of future code development.

HE-FUS3 benchmark results

Meloni, Paride;Polidori, Massimiliano
2012

Abstract

The assessment of numerical tools for the Safety Analysis of GFR and the demonstrator ALLEGRO is the objective of the GoFastR Task 1.5.3. The available experimental data related to the HEFUS3 (ENEA Brasimone, Italy) integraI facility cooled by helium are considered with reference to the 2009 experimental campaign. Seven organizations (ENEA, PSI, AEKI/CEA, KIT, NRG, RC-Rez) are involved in the benchmark exercise with six different codes (RELAP5, TRACE, CATHARE, SIM-GFR, SPECTRA and FLUENT). The capabilities of this wide spread of transient analysis codes to describe the T/H behavior of a helium system is verified both in steady-state and transient conditions (LOFA). On the basis of a code-to-code benchmark and code-to-experiment comparison, the present document summarizes the exercise outcomes, providing the descriptions of the code models as well as the main calculation results. Taking into account the limits of the HEFUS3 experimental data, the analysis of the results has led to a generaI positive evaluation of the codes performance, allowing to draw some recommendations on gas cooled systems modeling and the needs of future code development.
Rapporto tecnico;Generation IV reactors;Reattori nucleari a gas;Sicurezza nucleare;Analisi incidentale
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/7375
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