International Journal of Applied Ceramic Technology · 2010 · 75 citations · 28 references
EngineeringMaterials EngineeringMaterials ScienceCeramic MaterialsCeramicsNuclear MaterialsCeramic Nuclear MaterialsDefects In CeramicsMetalsRadiation Damage In MaterialsRadiation HardeningRadiation-resistant MaterialsCeramic Radiation DamageIon Irradiation DamageIrradiation DamageIrradiation Effects On MaterialsMicrostructureMicrostructure Evolution Under IrradiationRadiation Damage In CeramicsRadiation Damage Mechanisms
Ti 3 SiC 2 , belonging to MAX phases, is a potential candidate material, which could be incorporated in core components of future gas‐cooled fast nuclear reactors (GFR). Despite extensive work on mechanical behavior, corrosion resistance, or electrical properties, data concerning the evolution of Ti 3 SiC 2 under irradiation are very limited. In this work, Ti 3 (Si,Al)C 2 was irradiated at room temperature with 92 MeV Xe ions to induce irradiation damage. The samples were investigated by transmission electron microscopy (TEM) through front view and cross‐section observations, which allowed to follow microstructure changes from 0.02 dpa up to 6.67 dpa. Progressive atomic disorder versus dose was highlighted, leading to extinction of some diffraction spots (at 0.15 dpa) and then diffuse patterns (at 3 dpa). The ABABACAC periodicity related to 3‐1‐2 MAX phases was lost but the image fringes of basal plans could still be identified and no amorphous ring occurred. This means that Ti 3 (Si,Al)C 2 was strongly affected by irradiation but did not turn to amorphous even at 6.67 dpa. This important result was correlated to previous conclusions from X‐ray diffraction and nanoindentation analysis and suggests the good behavior of Ti 3 (Si,Al)C 2 under irradiation in the target temperature range assigned to GFR.
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Michel W. Barsoum, T. El‐Raghy, Claudia J. Rawn et al. · Journal of Physics and Chemistry of Solids · 1999 · 361 citations
Natural Sciences, Materials Engineering, Materials Science +12