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Title: Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C

Here, this work reports the first mechanical properties of Ti 3AlC 2-Ti 5Al 2C 3 materials neutron irradiated at ~400, 630 and 700 °C at a fluence of 2 × 10 25 n m -2 (E > 0.1 MeV) or a displacement dose of ~2 dpa. After irradiation at ~400 °C, anisotropic swelling and loss of 90% flexural strength was observed. After irradiation at ~630–700 °C, properties were unchanged. Microcracking and kinking-delamination had occurred during irradiation at ~630–700 °C. Further examination showed no cavities in Ti 3AlC 2 after irradiation at ~630 °C, and MX and A lamellae were preserved. However, disturbance of (0004) reflections corresponding to M-A layers was observed, and the number density of line/planar defects was ~10 23 m -3 of size 5–10 nm. HAADF identified these defects as antisite Ti Al atoms. Finally, Ti 3AlC 2-Ti 5Al 2C 3 shows abrupt dynamic recovery of A-layers from ~630 °C, but a higher temperature appears necessary for full recovery.
 [1] ;  [1] ;  [2] ;  [1] ;  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); General Atomics, San Diego, CA (United States)
Publication Date:
Grant/Contract Number:
Accepted Manuscript
Journal Name:
Journal of the European Ceramic Society
Additional Journal Information:
Journal Volume: 37; Journal Issue: 6; Journal ID: ISSN 0955-2219
Research Org:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR) and Spallation Neutron Source (SNS)
Sponsoring Org:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
Country of Publication:
United States
36 MATERIALS SCIENCE; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; MAX phase; neutron irradiation; mechanical properties; dynamic recovery; fracture
OSTI Identifier:
Alternate Identifier(s):
OSTI ID: 1417111