skip to main content
DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC

Abstract

Titanium carbide (TiC) is an ultra-high temperature ceramic with potential as a structural material candidate for advanced reactor concepts. However, the irradiation tolerance of TiC is not well understood. Here, we reveal the key irradiation damage microstructure degradation processes in TiC using mixed spectrum neutron irradiations at dose of ~2 displacements per atom (dpa) at temperatures of ~220, 620, and 1115 °C, combined with state-of-art microstructure characterization using transmission electron microscopy (TEM) and high-resolution TEM (HRTEM). The helium injection (~65 atomic parts per million) produced by neutron transmutation also occurred in the sample. TiC was observed to form irradiation-induced interstitial-type dislocation loops and He-stabilized cavities. At 220 and 620 °C, the analysis of the electron diffraction patterns, rel-rod imaging and HRTEM revealed that the dislocation loops were faulted Frank loops with Burgers vector bFrank = 1/3<111> lying on {111} planes. A detailed Burgers vector identification performed by the g.b technique revealed that the dislocation loops forming at 1115 °C were unfaulted, edge-type, with Burgers vectors b = a<100> and a/2<110> with corresponding {100} and {110} habit planes. Using continuum mechanics, we estimated the critical radius at which a faulted dislocation loop transitions to a perfect loop to be 9 nm.more » Further, no amorphization occurred in TiC under-investigated irradiation conditions while macroscopic swelling under point defect swelling regime was observed. He-stabilized cavities were detected at 1115 °C, but not at lower temperature irradiation. These observations indicate the onset of long-range vacancy migration in TiC occurs between 620 and 1115 °C.« less

Authors:
 [1]; ORCiD logo [2]; ORCiD logo [2];  [2]; ORCiD logo [2]; ORCiD logo [2];  [1]; ORCiD logo [3]
  1. Univ. of Tennessee, Knoxville, TN (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. 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)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1649527
Alternate Identifier(s):
OSTI ID: 1779346
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Acta Materialia
Additional Journal Information:
Journal Volume: 186; Journal Issue: 1; Journal ID: ISSN 1359-6454
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE

Citation Formats

Agarwal, Shradha, Koyanagi, Takaaki, Bhattacharya, Arunodaya, Wang, Ling, Kato, Yutai, Hu, Xunxiang, Pagan, Michael B., and Zinkle, Steven J.. Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC. United States: N. p., 2019. Web. https://doi.org/10.1016/j.actamat.2019.12.022.
Agarwal, Shradha, Koyanagi, Takaaki, Bhattacharya, Arunodaya, Wang, Ling, Kato, Yutai, Hu, Xunxiang, Pagan, Michael B., & Zinkle, Steven J.. Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC. United States. https://doi.org/10.1016/j.actamat.2019.12.022
Agarwal, Shradha, Koyanagi, Takaaki, Bhattacharya, Arunodaya, Wang, Ling, Kato, Yutai, Hu, Xunxiang, Pagan, Michael B., and Zinkle, Steven J.. Fri . "Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC". United States. https://doi.org/10.1016/j.actamat.2019.12.022. https://www.osti.gov/servlets/purl/1649527.
@article{osti_1649527,
title = {Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC},
author = {Agarwal, Shradha and Koyanagi, Takaaki and Bhattacharya, Arunodaya and Wang, Ling and Kato, Yutai and Hu, Xunxiang and Pagan, Michael B. and Zinkle, Steven J.},
abstractNote = {Titanium carbide (TiC) is an ultra-high temperature ceramic with potential as a structural material candidate for advanced reactor concepts. However, the irradiation tolerance of TiC is not well understood. Here, we reveal the key irradiation damage microstructure degradation processes in TiC using mixed spectrum neutron irradiations at dose of ~2 displacements per atom (dpa) at temperatures of ~220, 620, and 1115 °C, combined with state-of-art microstructure characterization using transmission electron microscopy (TEM) and high-resolution TEM (HRTEM). The helium injection (~65 atomic parts per million) produced by neutron transmutation also occurred in the sample. TiC was observed to form irradiation-induced interstitial-type dislocation loops and He-stabilized cavities. At 220 and 620 °C, the analysis of the electron diffraction patterns, rel-rod imaging and HRTEM revealed that the dislocation loops were faulted Frank loops with Burgers vector bFrank = 1/3<111> lying on {111} planes. A detailed Burgers vector identification performed by the g.b technique revealed that the dislocation loops forming at 1115 °C were unfaulted, edge-type, with Burgers vectors b = a<100> and a/2<110> with corresponding {100} and {110} habit planes. Using continuum mechanics, we estimated the critical radius at which a faulted dislocation loop transitions to a perfect loop to be 9 nm. Further, no amorphization occurred in TiC under-investigated irradiation conditions while macroscopic swelling under point defect swelling regime was observed. He-stabilized cavities were detected at 1115 °C, but not at lower temperature irradiation. These observations indicate the onset of long-range vacancy migration in TiC occurs between 620 and 1115 °C.},
doi = {10.1016/j.actamat.2019.12.022},
journal = {Acta Materialia},
number = 1,
volume = 186,
place = {United States},
year = {2019},
month = {12}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record

Citation Metrics:
Cited by: 3 works
Citation information provided by
Web of Science

Save / Share: