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Title: 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:
 [1];  [1];  [1];  [1];  [1]
  1. 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) (SC-22)
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. doi: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. doi: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 = {2015},
month = {7}
}

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