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Title: Effects of neutron irradiation of Ti 3SiC 2 and Ti 3AlC 2 in the 121–1085 °C temperature range

Herein we report on the formation of defects in response to neutron irradiation of polycrystalline Ti 3SiC 2 and Ti 3AlC 2 samples exposed to doses of 0.14±0.01, 1.6±0.1, and 3.4±0.1 displacements per atom (dpa) at irradiation temperatures of 121±12, 735±6 and 1085±68 °C. After irradiation to 0.14 dpa at 121 °C and 735 °C, black spots are observed in both Ti 3SiC 2 and Ti 3AlC 2. 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 Ti 3SiC 2, with loop diameters of 21±6 and 30±8 nm for 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. Voids are observed at grain boundaries and within stacking faults after 3.4 dpa irradiation, with extensive void formation in the TiC regions at 1085 °C. Remarkably, denuded zones on the order of 1 µm are observed in Ti 3SiC 2 after irradiationmore » 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 presence of the A-layer in the MAX phases is seen to provide enhanced irradiation tolerance. Based on these results, and up to 3.41 dpa, Ti 3SiC 2 remains a promising candidate for high temperature nuclear applications.« less
Authors:
 [1] ;  [2] ;  [2] ;  [3] ;  [4] ;  [1]
  1. Drexel Univ., Philadelphia, PA (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  3. Drexel Univ., Philadelphia, PA (United States); Nuclear Research Centre, Negev (Israel)
  4. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
Publication Date:
Report Number(s):
INL/JOU-16-38199
Journal ID: ISSN 0022-3115; PII: S0022311516311370
Grant/Contract Number:
AC07-05ID14517; AC07-051D14517
Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 484; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; dislocation loops; MAX phases; neutron irradiation; Ti3AlC2; Ti3SiC2
OSTI Identifier:
1357614
Alternate Identifier(s):
OSTI ID: 1396851

Tallman, Darin J., He, Lingfeng, Gan, Jian, Caspi, El'ad N., Hoffman, Elizabeth N., and Barsoum, Michel W.. Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085 °C temperature range. United States: N. p., Web. doi:10.1016/j.jnucmat.2016.11.016.
Tallman, Darin J., He, Lingfeng, Gan, Jian, Caspi, El'ad N., Hoffman, Elizabeth N., & Barsoum, Michel W.. Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085 °C temperature range. United States. doi:10.1016/j.jnucmat.2016.11.016.
Tallman, Darin J., He, Lingfeng, Gan, Jian, Caspi, El'ad N., Hoffman, Elizabeth N., and Barsoum, Michel W.. 2016. "Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085 °C temperature range". United States. doi:10.1016/j.jnucmat.2016.11.016. https://www.osti.gov/servlets/purl/1357614.
@article{osti_1357614,
title = {Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085 °C temperature range},
author = {Tallman, Darin J. and He, Lingfeng and Gan, Jian and Caspi, El'ad N. and Hoffman, Elizabeth N. and Barsoum, Michel W.},
abstractNote = {Herein we report on the formation of defects in response to neutron irradiation of polycrystalline Ti3SiC2 and Ti3AlC2 samples exposed to doses of 0.14±0.01, 1.6±0.1, and 3.4±0.1 displacements per atom (dpa) at irradiation temperatures of 121±12, 735±6 and 1085±68 °C. After irradiation to 0.14 dpa at 121 °C and 735 °C, black spots are observed 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 for 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. Voids are observed at grain boundaries and within stacking faults after 3.4 dpa irradiation, with extensive void 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 presence of the A-layer in the MAX phases is seen to provide enhanced irradiation tolerance. Based on these results, and up to 3.41 dpa, Ti3SiC2 remains a promising candidate for high temperature nuclear applications.},
doi = {10.1016/j.jnucmat.2016.11.016},
journal = {Journal of Nuclear Materials},
number = C,
volume = 484,
place = {United States},
year = {2016},
month = {11}
}