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.
|Journal||The Journal of The Minerals, Metals & Materials Society|
|State||Published - Jan 2005|