Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys
Abstract
The Fe Cr Al alloy system has the potential to form an important class of enhanced accident-tolerant cladding materials in the nuclear power industry owing to the alloy system's higher oxidation resistance in high-temperature steam environments compared with traditional zirconium-based alloys. However, radiation tolerance of Fe Cr Al alloys has not been fully established. In this study, a series of Fe Cr Al alloys with 10 18 wt % Cr and 2.9 4.9 wt % Al were neutron irradiated at 382 C to 1.8 dpa to investigate the irradiation-induced microstructural and mechanical property evolution as a function of alloy composition. Dislocation loops with Burgers vector of a/2 111 and a 100 were detected and quantified. Results indicate precipitation of Cr-rich is primarily dependent on the bulk chromium composition. Mechanical testing of sub-size-irradiated tensile specimens indicates the hardening response seen after irradiation is dependent on the bulk chromium composition. Furthermore, a structure property relationship was developed; it indicated that the change in yield strength after irradiation is caused by the formation of these radiation-induced defects and is dominated by the large number density of Cr-rich α' precipitates at sufficiently high chromium contents after irradiation.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES)
- OSTI Identifier:
- 1195807
- Alternate Identifier(s):
- OSTI ID: 1251989
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 465; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; FeCrAl; accident tolerant; phase stability; dislocation; hardening
Citation Formats
Field, Kevin G., Hu, Xunxiang, Littrell, Kenneth C., Yamamoto, Yukinori, and Snead, Lance Lewis. Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys. United States: N. p., 2015.
Web. doi:10.1016/j.jnucmat.2015.06.023.
Field, Kevin G., Hu, Xunxiang, Littrell, Kenneth C., Yamamoto, Yukinori, & Snead, Lance Lewis. Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys. United States. https://doi.org/10.1016/j.jnucmat.2015.06.023
Field, Kevin G., Hu, Xunxiang, Littrell, Kenneth C., Yamamoto, Yukinori, and Snead, Lance Lewis. Tue .
"Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys". United States. https://doi.org/10.1016/j.jnucmat.2015.06.023. https://www.osti.gov/servlets/purl/1195807.
@article{osti_1195807,
title = {Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys},
author = {Field, Kevin G. and Hu, Xunxiang and Littrell, Kenneth C. and Yamamoto, Yukinori and Snead, Lance Lewis},
abstractNote = {The Fe Cr Al alloy system has the potential to form an important class of enhanced accident-tolerant cladding materials in the nuclear power industry owing to the alloy system's higher oxidation resistance in high-temperature steam environments compared with traditional zirconium-based alloys. However, radiation tolerance of Fe Cr Al alloys has not been fully established. In this study, a series of Fe Cr Al alloys with 10 18 wt % Cr and 2.9 4.9 wt % Al were neutron irradiated at 382 C to 1.8 dpa to investigate the irradiation-induced microstructural and mechanical property evolution as a function of alloy composition. Dislocation loops with Burgers vector of a/2 111 and a 100 were detected and quantified. Results indicate precipitation of Cr-rich is primarily dependent on the bulk chromium composition. Mechanical testing of sub-size-irradiated tensile specimens indicates the hardening response seen after irradiation is dependent on the bulk chromium composition. Furthermore, a structure property relationship was developed; it indicated that the change in yield strength after irradiation is caused by the formation of these radiation-induced defects and is dominated by the large number density of Cr-rich α' precipitates at sufficiently high chromium contents after irradiation.},
doi = {10.1016/j.jnucmat.2015.06.023},
journal = {Journal of Nuclear Materials},
number = ,
volume = 465,
place = {United States},
year = {Tue Jul 14 00:00:00 EDT 2015},
month = {Tue Jul 14 00:00:00 EDT 2015}
}
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