On the basis of the results obtained in the 2009 experimental campaign conducted in the HE-FUS3 loop (CR BRASIMONE) within the framework of the first year of the AdP ENEA-MSE a new experimental campaign has been planned for the second year for the following reasons: - the post-tests calculations performed with the RELAP5 code showed for some tests a lack of important information on the facility behaviour in transient conditions that would require the repetition of the tests with an upgraded instrumentation, - new experimental tests conducted at higher pressure and mass flowrate considering previous and additional transient scenarios would allow to enlarge the experimental data base for the assessment of thermal-hydraulic codes used for HTR and VHTR design and safety analysis As for the previous year the definition of the test matrix has been supported with pre-test calculations carried out with the T/H system code RELAP5. To this purpose the HE-FUS3 model assessed in the post-test activity has been used with minor modifications.

Pre-Test Analysis for an Experimental Campaign in the Upgraded HE-FUS3 Loop

Nitti, F.;Meloni, P.
2010-09-15

Abstract

On the basis of the results obtained in the 2009 experimental campaign conducted in the HE-FUS3 loop (CR BRASIMONE) within the framework of the first year of the AdP ENEA-MSE a new experimental campaign has been planned for the second year for the following reasons: - the post-tests calculations performed with the RELAP5 code showed for some tests a lack of important information on the facility behaviour in transient conditions that would require the repetition of the tests with an upgraded instrumentation, - new experimental tests conducted at higher pressure and mass flowrate considering previous and additional transient scenarios would allow to enlarge the experimental data base for the assessment of thermal-hydraulic codes used for HTR and VHTR design and safety analysis As for the previous year the definition of the test matrix has been supported with pre-test calculations carried out with the T/H system code RELAP5. To this purpose the HE-FUS3 model assessed in the post-test activity has been used with minor modifications.
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: http://hdl.handle.net/20.500.12079/5469
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