Materials for Accelerator Driven System

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High Chromium ferritic martensitic steels and austenitic steels that are foreseen as candidates to build a spallation target as well as fuel claddings were irradiated in BR2 reactor at 200°C. The post irradiation examination of the irradiated materials, that consist of slow rate tensile testing them in a liquid metal environment, demonstrates that they conserve their performance. The liquid metal embrittlement seems to be hindered by the self healing mechanism.


Original languageEnglish
Pages (from-to)69-70
JournalThe Journal of The Minerals, Metals & Materials Society
Issue number3
Publication statusPublished - Jan 2005


  • Liquid metal embrittlement, neutron irradiation

ID: 309144