"Effect of neutron irradiation on defect evolution in Ti3SiC2 and Ti2AlC"
Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, Brenda Garcia-Diaz, Robert Sindelar,
Journal of Nuclear materials
Vol. 468
2015
1-13
Link
Herein we report on the characterization of defects formed in polycrystalline Ti3SiC2 and Ti2AlC samples
exposed to neutron irradiation e 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 ¼ 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 wasz1.5 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. |
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"Effect of neutron irradiation on select MAX phases"
Michel Barsoum, Elizabeth Hoffman, Gordon Kohse, Darin Tallman,
Acta Materialia
Vol. 85
2014
132-143
Link
Abstract—Herein we report on the effect of neutron irradiation – of up to 0.1 displacements per atom at 360(20) C or 695(25) C – on polycrystalline samples of Ti3AlC2, Ti2AlC, Ti3SiC2 and Ti2AlN. Rietveld refinement of X-ray diffraction patterns of the irradiated samples showed irradiation enhanced
dissociation into TiC of the Ti3AlC2 and Ti3SiC2 phases, most prominently in the former. Ti2AlN also showed an increase in TiN content,
as well as Ti4AlN3 after irradiation. In contrast, Ti2AlC was quite stable under these irradiation conditions. Dislocation loops are seen to form in Ti2AlC and Ti3AlC2 after irradiation at 360(20) C. The room temperature electrical resistivity of all samples increased by an order of magnitude after irradiation at 360(20) C, but only by 25% after 695(25) C, providing evidence for the MAX phases’ dynamic recovery at temperatures as low at 695(25) C. Based on these preliminary results, it appears that Ti2AlC and Ti3SiC2 are the more promising materials for high-temperature nuclear applications. |
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"Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121-1085 C temperature range"
Michel Barsoum, Jian Gan, Elizabeth Hoffman, Darin Tallman, Lingfeng He, El'ad Caspi,
Journal of Nuclear Materials
Vol. 484
2017
120-134
Link
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. |
"Effect of Neutron Irradiation on Mn+1AXn phases" Michel Barsoum, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, ICACC'14 January 27-31, (2014) | |
"Effect of Neutron Irradiation on Mn+1AXn phases" Michel Barsoum, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, TMS2014 February 15-19, (2014) | |
"Effect of Neutron Irradiation on Select Mn+1AXn phases" Michel Barsoum, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, CIMTEC'14 June 10-15, (2014) | |
"Microstructural Defects in Neutron Irradiated Ti3SiC2 and Ti2AlC" Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, ICACC'15 January 25-29, (2015) | |
"Neutron Irradiation of MAX Phases" Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, Il Trovatore Meeting 2 July 23-25, (2015) | |
"Nuclear Scientific User Facility: Neutron Irradiation of MAX Phases" Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, NSUF User's Week June 22-26, (2015) | |
"The Effect of Neutron Irradiation on select MAX phases" Michel Barsoum, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, International Conference and Exposition on Advanced Ceramics and Composites (ICACC) January 31-31, (2013) Link |
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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