This document deals with deterministic analyses of Lithium LOCA in the Lithium Loop Area of the IFMIF target facility performed with the RELAP code. The activity is part of a long cooperation between FIS-NUC and FUS-TEC sections on IFMIF Facility safety studies. Some modifications in the original IFMIF RELAP5 nodalization have been necessary to allow the simulation of the LOCA transients. Different break size conditions have been investigated in order to determine the system safety margin with respect to the target back plate damage, in term of the grace time to manual recover the accident in case of the protection system failure. An evaluation of this time at differed conditions is provided in the report together with an accurate specification of the limits of the numerical model used, which can affect the confidence on the numerical results.

IFMIF Lithium LOCA Analyses with RELAP5 Code

Meloni, P.
2006-03-01

Abstract

This document deals with deterministic analyses of Lithium LOCA in the Lithium Loop Area of the IFMIF target facility performed with the RELAP code. The activity is part of a long cooperation between FIS-NUC and FUS-TEC sections on IFMIF Facility safety studies. Some modifications in the original IFMIF RELAP5 nodalization have been necessary to allow the simulation of the LOCA transients. Different break size conditions have been investigated in order to determine the system safety margin with respect to the target back plate damage, in term of the grace time to manual recover the accident in case of the protection system failure. An evaluation of this time at differed conditions is provided in the report together with an accurate specification of the limits of the numerical model used, which can affect the confidence on the numerical results.
Rapporto tecnico;Reattori nucleari a fusione;Sicurezza nucleare;Analisi incidentale
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/7002
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