Abstract
Abstract Because of good damage tolerance, thermal stability and interesting mechanical properties, Ti3SiC2, belonging to Mn+1AXn phases, has been considered as a potential candidate material for applications in the future Gas Fast nuclear Reactors (GFR) such as components of fuel cladding working between 500 °C and 800 °C. However, the outstanding mechanical properties of Ti3SiC2 related to a layered microstructure could be impacted by irradiation. In this work, high energy Kr and Xe ion irradiated Ti3Si0.95Al0.05C2 and Ti3Si0.90Al0.10C2 samples, provided by IMR Shenyang, Chinese Academy of Science, were characterized by nanoindentation technique. After irradiation at room temperature, an increase in hardness with irradiation dose was highlighted. Nevertheless, some damage tolerance remained because of preservation of the typical MAX layered structure. Irradiations at 300 °C and 500 °C lead to less significant increase suggesting irradiation defect annealing. A complete recovery of the properties at 800 °C seems to be obtained.
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