Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2-Ti5Al2C3 materials
Abstract
Mn + 1AXn (MAX) phase materials based on Ti–Al–C have been irradiated at 400 °C (673 K) with fission neutrons to a fluence of 2 × 1025 n/m2 (E > 0.1 MeV), corresponding to ~ 2 displacements per atom (dpa). We report preliminary results of microcracking in the Al-containing MAX phase, which contained the phases Ti3AlC2 and Ti5Al2C3. Equibiaxial ring-on-ring tests of irradiated coupons showed that samples retained 10% of pre-irradiated strength. Volumetric swelling of up to 4% was observed. Phase analysis and microscopy suggest that anisotropic lattice parameter swelling caused microcracking. Lastly, variants of titanium aluminum carbide may be unsuitable materials for irradiation at light water reactor-relevant temperatures.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Temperature Materials Lab. (HTML); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Spallation Neutron Source (SNS)
- Sponsoring Org.:
- USDOE Office of Science (SC)
- OSTI Identifier:
- 1234339
- Alternate Identifier(s):
- OSTI ID: 1460447
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Scripta Materialia
- Additional Journal Information:
- Journal Volume: 114; Journal Issue: C; Journal ID: ISSN 1359-6462
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS
Citation Formats
Ang, Caen K., Silva, Chinthaka M., Shih, Chunghao Phillip, Koyanagi, Takaaki, Katoh, Yutai, and Zinkle, Steven J. Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2-Ti5Al2C3 materials. United States: N. p., 2015.
Web. doi:10.1016/j.scriptamat.2015.11.008.
Ang, Caen K., Silva, Chinthaka M., Shih, Chunghao Phillip, Koyanagi, Takaaki, Katoh, Yutai, & Zinkle, Steven J. Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2-Ti5Al2C3 materials. United States. https://doi.org/10.1016/j.scriptamat.2015.11.008
Ang, Caen K., Silva, Chinthaka M., Shih, Chunghao Phillip, Koyanagi, Takaaki, Katoh, Yutai, and Zinkle, Steven J. Thu .
"Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2-Ti5Al2C3 materials". United States. https://doi.org/10.1016/j.scriptamat.2015.11.008. https://www.osti.gov/servlets/purl/1234339.
@article{osti_1234339,
title = {Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2-Ti5Al2C3 materials},
author = {Ang, Caen K. and Silva, Chinthaka M. and Shih, Chunghao Phillip and Koyanagi, Takaaki and Katoh, Yutai and Zinkle, Steven J.},
abstractNote = {Mn + 1AXn (MAX) phase materials based on Ti–Al–C have been irradiated at 400 °C (673 K) with fission neutrons to a fluence of 2 × 1025 n/m2 (E > 0.1 MeV), corresponding to ~ 2 displacements per atom (dpa). We report preliminary results of microcracking in the Al-containing MAX phase, which contained the phases Ti3AlC2 and Ti5Al2C3. Equibiaxial ring-on-ring tests of irradiated coupons showed that samples retained 10% of pre-irradiated strength. Volumetric swelling of up to 4% was observed. Phase analysis and microscopy suggest that anisotropic lattice parameter swelling caused microcracking. Lastly, variants of titanium aluminum carbide may be unsuitable materials for irradiation at light water reactor-relevant temperatures.},
doi = {10.1016/j.scriptamat.2015.11.008},
journal = {Scripta Materialia},
number = C,
volume = 114,
place = {United States},
year = {Thu Dec 17 00:00:00 EST 2015},
month = {Thu Dec 17 00:00:00 EST 2015}
}
Web of Science
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Works referencing / citing this record:
An Overview of Parameters Controlling the Decomposition and Degradation of Ti-Based Mn+1AXn Phases
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