This report reports the results of an experimental campaign performed in the HE-FUS 3 facility in order to provide a reliable experimental data base far the assessment of thermal-hydraulic codes used far High Temperature Reactor (HTR) and Very High Temperature Reactor (VHTR) design and safety analysis. Moreover, the campaign was also addressed to a complete characterization of the helium loop. In particular, the plant start-up by steps was carried aut in order to collect data at different steady state conditions far the characterization of the heat Iosses and compressor performances. A set of transients representative of operational and accident conditions that are of particular meaning far the assessment of T/H cades were performed in order to obtain relevant experimental data. These tests consisted of two Loss of Flow Accidents with a different dynamic of the accidental event and two Loss of Coolant Accidents at different loop pressure. In this technical report the 7-pin Test Section, specifically assembled far this test campaign, the circuit, modified to host the Test Section, and the achieved results are described.

HE-FUS 3 EXPERIMENTAL CAMPAIGN FOR THE ASSESSMENT OF THERMAL-HYDRAULIC CODES: EXPERIMENT DATA REPORT

Monti, S.
2009

Abstract

This report reports the results of an experimental campaign performed in the HE-FUS 3 facility in order to provide a reliable experimental data base far the assessment of thermal-hydraulic codes used far High Temperature Reactor (HTR) and Very High Temperature Reactor (VHTR) design and safety analysis. Moreover, the campaign was also addressed to a complete characterization of the helium loop. In particular, the plant start-up by steps was carried aut in order to collect data at different steady state conditions far the characterization of the heat Iosses and compressor performances. A set of transients representative of operational and accident conditions that are of particular meaning far the assessment of T/H cades were performed in order to obtain relevant experimental data. These tests consisted of two Loss of Flow Accidents with a different dynamic of the accidental event and two Loss of Coolant Accidents at different loop pressure. In this technical report the 7-pin Test Section, specifically assembled far this test campaign, the circuit, modified to host the Test Section, and the achieved results are described.
Rapporto tecnico;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/20.500.12079/7333
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