This report has been issued in the frame of the ENEA and MSE research program on "Nuovo Nucleare da fissione". It is the deliverable A.1-1 of the task LP2 of the work program 2008-2009 'Verifiche analitiche a supporto del progetto' della facility SPES3. The document deals with the results of RELAP5 simulations of the DVI line DEG break for design and beyond design basis conditions. It describes the influence of PCC and ADS. Stage-II actuation time on accident recovery. A comparison between fuIl power and reduced power steady state conditions is reported together with a comparison between transients starting from such conditions. The results demonstrate that SPES3 facility is suitable to simulate accidental transients starting from reduced power and mass flow conditions with little differences by transients starting from full power.

SPES3 facility: RELAP5 simulations of the DBE and BDBE DVI line DEG break from 65% and 100% power for design support

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2011-08-10

Abstract

This report has been issued in the frame of the ENEA and MSE research program on "Nuovo Nucleare da fissione". It is the deliverable A.1-1 of the task LP2 of the work program 2008-2009 'Verifiche analitiche a supporto del progetto' della facility SPES3. The document deals with the results of RELAP5 simulations of the DVI line DEG break for design and beyond design basis conditions. It describes the influence of PCC and ADS. Stage-II actuation time on accident recovery. A comparison between fuIl power and reduced power steady state conditions is reported together with a comparison between transients starting from such conditions. The results demonstrate that SPES3 facility is suitable to simulate accidental transients starting from reduced power and mass flow conditions with little differences by transients starting from full power.
Rapporto tecnico;Reattori nucleari ad acqua
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/5454
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