Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085 °C temperature range

Darin J. Tallman; Lingfeng He; Jian Gan; El'ad N. Caspi; Elizabeth N. Hoffman; Michel W. Barsoum; Elad N Caspi

doi:10.1016/j.jnucmat.2016.11.016

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Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085 °C temperature range

Journal article

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Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085 °C temperature range

Darin J. Tallman, Lingfeng He, Jian Gan, El'ad N. Caspi, Elizabeth N. Hoffman, Michel W. Barsoum and Elad N Caspi

Journal of nuclear materials, v 484

Feb 2017

DOI: https://doi.org/10.1016/j.jnucmat.2016.11.016

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Abstract

Dislocation loops

MAX phases

Neutron irradiation

Ti3AlC2

Ti3SiC2

Herein we report on the formation of defects in response to neutron irradiation of polycrystalline Ti3SiC2 and Ti3AlC2 samples exposed to total fluences of ≈6 × 1020 n/m2, 5 × 1021 n/m2 and 1.7 × 1022 n/m2 at irradiation temperatures of 121(12), 735(6) and 1085(68)°C. These fluences correspond to 0.14, 1.6 and 3.4 dpa, respectively. After irradiation to 0.14 dpa at 121 °C and 735 °C, black spots are observed via transmission electron microscopy in both Ti3SiC2 and Ti3AlC2. After irradiation to 1.6 and 3.4 dpa at 735 °C, basal dislocation loops, with a Burgers vector of b = ½ [0001] are observed in Ti3SiC2, with loop diameters of 21(6) and 30(8) nm after 1.6 dpa and 3.4 dpa, respectively. In Ti3AlC2, larger dislocation loops, 75(34) nm in diameter are observed after 3.4 dpa at 735 °C, in addition to stacking faults. Impurity particles of TiC, as well as stacking fault TiC platelets in the MAX phases, are seen to form extensive dislocation loops under all conditions. Cavities were observed at grain boundaries and within stacking faults after 3.4 dpa irradiation, with extensive cavity formation in the TiC regions at 1085 °C. Remarkably, denuded zones on the order of 1 μm are observed in Ti3SiC2 after irradiation to 3.4 dpa at 735 °C. Small grains, 3–5 μm in diameter, are damage free after irradiation at 1085 °C at this dose. The results shown herein confirm once again that the presence of the A-layers in the MAX phases considerably enhance their irradiation tolerance. Based on these results, and up to 3.4 dpa, Ti3SiC2 remains a promising candidate for high temperature nuclear applications as long as the temperature remains >700 °C.

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Details

Title: Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085 °C temperature range
Creators: Darin J. Tallman - Drexel University
Lingfeng He - Idaho National Laboratory
Jian Gan - Idaho National Laboratory
El'ad N. Caspi - Department of Materials Science and Engineering, Drexel University, Philadelphia, PA 19104, United States
Elizabeth N. Hoffman - Savannah River National Laboratory
Michel W. Barsoum - Drexel University
Elad N Caspi - Materials Science and Engineering
Publication Details: Journal of nuclear materials, v 484
Publisher: Elsevier
Resource Type: Journal article
Language: English
Academic Unit: Materials Science and Engineering
Web of Science ID: WOS:000393246300015
Scopus ID: 2-s2.0-85000956312
Other Identifier: 991019168660604721

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