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Effect of neutron irradiation on defect evolution in Ti3SiC2 and Ti2AlC
Journal article   Open access   Peer reviewed

Effect of neutron irradiation on defect evolution in Ti3SiC2 and Ti2AlC

Darin J. Tallman, Lingfeng He, Brenda L. Garcia-Diaz, Elizabeth N. Hoffman, Gordon Kohse, Robert L. Sindelar and Michel W. Barsoum
Journal of nuclear materials, v 468, pp 194-206
Jan 2016
url
https://doi.org/10.1016/j.jnucmat.2015.10.030View
Accepted (AM)Open Access (Publisher-Specific) Open

Abstract

Dislocation loops MAX phases Neutron irradiation Ti2AlC Ti3SiC2
Herein we report on the characterization of defects formed in polycrystalline Ti3SiC2 and Ti2AlC samples exposed to neutron irradiation – up to 0.1 displacements per atom (dpa) at 350 ± 40 °C or 695 ± 25 °C, and up to 0.4 dpa at 350 ± 40 °C. Black spots are observed in both Ti3SiC2 and Ti2AlC after irradiation to both 0.1 and 0.4 dpa at 350 °C. After irradiation to 0.1 dpa at 695 °C, small basal dislocation loops, with a Burgers vector of b = 1/2 [0001] are observed in both materials. At 9 ± 3 and 10 ± 5 nm, the loop diameters in the Ti3SiC2 and Ti2AlC samples, respectively, were comparable. At 1 × 1023 loops/m3, the dislocation loop density in Ti2AlC was ≈1.5 orders of magnitude greater than in Ti3SiC2, at 3 × 1021 loops/m3. After irradiation at 350 °C, extensive microcracking was observed in Ti2AlC, but not in Ti3SiC2. The room temperature electrical resistivities increased as a function of neutron dose for all samples tested, and appear to saturate in the case of Ti3SiC2. The MAX phases are unequivocally more neutron radiation tolerant than the impurity phases TiC and Al2O3. Based on these results, Ti3SiC2 appears to be a more promising MAX phase candidate for high temperature nuclear applications than Ti2AlC. •Neutron irradiation induced defects in Ti3SiC2 and Ti2AlC were investigated.•At 0.1 dpa at 695 °C, basal dislocation loops formed in both materials.•Ti2AlC showed 1.5 orders of magnitude higher loop density than Ti3SiC2.•The Burgers vector of all loops observed was b = 1/2 [0001].•The A-layer in the MAX phases provides significant irradiation tolerance.

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Collaboration types
Domestic collaboration
Web of Science research areas
Materials Science, Multidisciplinary
Nuclear Science & Technology
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