The present work has been performed within the framework of FP7 – LEADER project. The aim of this document is to provide a preliminary evaluation of the radiation damage of the structural materials of the ALFRED reactor (Advanced Lead-cooled Fast Reactor European Demonstrator) through the computation of the standard damage parameter for the nuclear materials (the DPA), an estimation of the activation of the structural materials and of the lead coolant, as well as the computation of the neutron and gamma doses in some key points of interest from radioprotection point of view. This document has been issued by INR in collaboration with ENEA.

ETDR core: DPA rates in the main components, activation, doses

Petrovich, Carlo;
2013

Abstract

The present work has been performed within the framework of FP7 – LEADER project. The aim of this document is to provide a preliminary evaluation of the radiation damage of the structural materials of the ALFRED reactor (Advanced Lead-cooled Fast Reactor European Demonstrator) through the computation of the standard damage parameter for the nuclear materials (the DPA), an estimation of the activation of the structural materials and of the lead coolant, as well as the computation of the neutron and gamma doses in some key points of interest from radioprotection point of view. This document has been issued by INR in collaboration with ENEA.
Rapporto tecnico;Reattori nucleari veloci;Generation IV reactors;Reattori e sistemi innovativi
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/7501
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