Mechanical Behavior of Neutron Inrradiated High Cr Ferritic-Martensitic Steels

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High Chromium Ferritic-Martensitic steels are candidate materials for the target spallation source and the fuel cladding tubes in the European demonstrator of the accelerator driven system (ADS). In this work, we will present new results obtained from the irradiation campaign that has been performed in the BR2 reactor within the SPIRE project to assess the mechanical behaviour of several standard 9-12%Cr steels. The irradiations have been performed up to 4.5 dpa at 200°C. A quantitative assessment of the effects of neutron irradiation, in terms of both hardening ) and embrittlement is presented, based on the comparison with the unirradiated


Original languageEnglish
Pages (from-to)73-74
JournalThe Journal of The Minerals, Metals & Materials Society
Issue number3
Publication statusPublished - 14 Oct 2005


  • Nuclear materials and environmental effects

ID: 193460