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

Ang, Caen; Parish, Chad M.; Shih, Chunghao; Silva, Chinthaka; Katoh, Yutai

doi:10.1016/j.jeurceramsoc.2017.01.024

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

Abstract

Here, this work reports the first mechanical properties of Ti₃AlC₂-Ti₅Al₂C₃ materials neutron irradiated at ~400, 630 and 700 °C at a fluence of 2 × 10²⁵ 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 Ti₃AlC₂ 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 ~10²³ m^-3 of size 5–10 nm. HAADF identified these defects as antisite Ti_Al atoms. Finally, Ti₃AlC₂-Ti₅Al₂C₃ shows abrupt dynamic recovery of A-layers from ~630 °C, but a higher temperature appears necessary for full recovery.

Authors:

Ang, Caen ^[1]; Parish, Chad M. ^[1]; Shih, Chunghao ^[2]; Silva, Chinthaka ^[1]; Katoh, Yutai ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); General Atomics, San Diego, CA (United States)

Publication Date:: Thu Feb 23 00:00:00 EST 2017

Research Org.:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

OSTI Identifier:: 1355877

Alternate Identifier(s):: OSTI ID: 1417111

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Journal of the European Ceramic Society

Additional Journal Information:: Journal Volume: 37; Journal Issue: 6; Journal ID: ISSN 0955-2219

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; MAX phase; neutron irradiation; mechanical properties; dynamic recovery; fracture

Citation Formats


                    Ang, Caen, Parish, Chad M., Shih, Chunghao, Silva, Chinthaka, and Katoh, Yutai. Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C.  United States: N. p., 2017. 
Web.  doi:10.1016/j.jeurceramsoc.2017.01.024.

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                    Ang, Caen, Parish, Chad M., Shih, Chunghao, Silva, Chinthaka, & Katoh, Yutai. Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C.  United States.  https://doi.org/10.1016/j.jeurceramsoc.2017.01.024

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                    Ang, Caen, Parish, Chad M., Shih, Chunghao, Silva, Chinthaka, and Katoh, Yutai. Thu .  
"Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C".  United States.  https://doi.org/10.1016/j.jeurceramsoc.2017.01.024.  https://www.osti.gov/servlets/purl/1355877.

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@article{osti_1355877,

  title        = {Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C},

  author       = {Ang, Caen and Parish, Chad M. and Shih, Chunghao and Silva, Chinthaka and Katoh, Yutai},

  abstractNote = {Here, this work reports the first mechanical properties of Ti3AlC2-Ti5Al2C3 materials neutron irradiated at ~400, 630 and 700 °C at a fluence of 2 × 1025 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 Ti3AlC2 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 ~1023 m-3 of size 5–10 nm. HAADF identified these defects as antisite TiAl atoms. Finally, Ti3AlC2-Ti5Al2C3 shows abrupt dynamic recovery of A-layers from ~630 °C, but a higher temperature appears necessary for full recovery.},

  doi          = {10.1016/j.jeurceramsoc.2017.01.024},

  journal      = {Journal of the European Ceramic Society},

  number       = 6,

  volume       = 37,

  place        = {United States},

  year         = {Thu Feb 23 00:00:00 EST 2017},

  month        = {Thu Feb 23 00:00:00 EST 2017}

}

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Works referencing / citing this record:

An Overview of Parameters Controlling the Decomposition and Degradation of Ti-Based Mn+1AXn Phases
journal, February 2019

Low, It-Meng
Materials, Vol. 12, Issue 3
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Title: Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C

Abstract

Citation Formats

The MN+1AXN phases: A new class of solids: Thermodynamically stable nanolaminates journal, January 2000

Handbook of SiC properties for fuel performance modeling journal, September 2007

Fully reversible, dislocation-based compressive deformation of Ti3SiC2 to 1 GPa journal, January 2003

Kinking nonlinear elastic deformation of Ti3AlC2, Ti2AlC, Ti3Al(C0.5,N0.5)2 and Ti2Al(C0.5,N0.5) journal, May 2010

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Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials journal, March 2016

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Concentric ring on ring test for unirradiated and irradiated miniature SiC specimens journal, October 2011

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Nomenclature of polytype structures. Report of the International Union of Crystallography Ad hoc Committee on the Nomenclature of Disordered, Modulated and Polytype Structures journal, July 1984

Thermal and Irradiation Creep Behavior of a Titanium Aluminide in Advanced Nuclear Plant Environments journal, September 2009

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Synthesis and Characterization of a Remarkable Ceramic: Ti3SiC2 journal, July 1996

Ab initio study of irradiation tolerance for different M n+1 AX n phases: Ti 3 SiC 2 and Ti 3 AlC 2 journal, January 2014

Effect of helium irradiation on Ti3AlC2 at 500°C journal, April 2014

Damage accumulation and recovery in C+-irradiated Ti3SiC2 journal, March 2014

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Fully reversible, dislocation-based compressive deformation of Ti3SiC2 to 1 GPa
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Displacement damage in silicon carbide irradiated in fission reactors
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Ab-initio structure determination of LiSbWO6 by X-ray powder diffraction
journal, March 1988

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journal, February 2014

Concentric ring on ring test for unirradiated and irradiated miniature SiC specimens
journal, October 2011

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Measurement of local thickness by electron energy-loss spectroscopy
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Structure of a new bulk Ti5Al2C3 MAX phase produced by the topotactic transformation of Ti2AlC
journal, September 2012

Nomenclature of polytype structures. Report of the International Union of Crystallography Ad hoc Committee on the Nomenclature of Disordered, Modulated and Polytype Structures
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Effect of helium irradiation on Ti3AlC2 at 500°C
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