This report concerns the preliminary design and the neutronic characterization of the ALFRED core (Advanced Lead-cooled Fast Reactor European Demonstrator), a criticaI reactor (300 MWth) for the demonstration ofthe Lead-cooled Fast Reactor technology chain in the framework ofthe LEADER project (VII EURATOM FP). Here the materials specifications, the core design and configuration, the power deposition distribution, the controllsafety systems, the feedback reactivity effects, the irradiated fuel composition and the burnup swing are reported. The used codes are MCNPX and ERANOS. This work has been performed by ENEA and CEA, in collaboration with SCK-CEN.

D07 - Definition of the ETDR core and neutronic characterization - PART I

Rocchi, F.;Grasso, C.;Petrovich, C.
2013-03-07

Abstract

This report concerns the preliminary design and the neutronic characterization of the ALFRED core (Advanced Lead-cooled Fast Reactor European Demonstrator), a criticaI reactor (300 MWth) for the demonstration ofthe Lead-cooled Fast Reactor technology chain in the framework ofthe LEADER project (VII EURATOM FP). Here the materials specifications, the core design and configuration, the power deposition distribution, the controllsafety systems, the feedback reactivity effects, the irradiated fuel composition and the burnup swing are reported. The used codes are MCNPX and ERANOS. This work has been performed by ENEA and CEA, in collaboration with SCK-CEN.
Rapporto tecnico;Generation IV reactors
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/7369
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