In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation
Abstract
This study characterizes the microstructural evolution of single-phase complex concentrated solid-solution alloy (CSA) compositions under heavy ion irradiation with the goal of evaluating mechanisms for CSA radiation tolerance in advanced fission systems. Three such alloys, Cr18Fe27Mn27Ni 28, Cr15Fe35Mn15Ni35, and equimolar NbTaTiV, along with reference materials (pure Ni and E90 for the Cr-FeMnNi family and pure V for NbTaTiV) were irradiated at 50 K and 773 K with 1 MeV Kr++ ions to various levels of displacements per atom (dpa) using in-situ transmission electron microscopy. Cryogenic irradiation resulted in small defect clusters and faulted dislocation loops as large as 12 nm in face-centered cubic (FCC) CSAs. With thermal diffusion suppressed at cryogenic temperatures, defect densities were lower in all CSAs than in their less compositionally complex reference materials indicating that point defect production is reduced during the displacement cascade stage. High temperature irradiation of the two FCC CSA resulted in the formation of interstitial dislocation loops which by 2 dpa grew to an average size of 27 nm in Cr18Fe27Mn27Ni28 and 10 nm in Cr15Fe35Mn15Ni35. This difference in loop growth kinetics was attributed to the difference in Mn-content due to its effect on the nucleation rate by increasing vacancy mobility ormore »
- Authors:
-
- Univ. of Wisconsin, Madison, WI (United States)
- Argonne National Lab. (ANL), Lemont, IL (United States)
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Org.:
- National Science Foundation (NSF); USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1776842
- Alternate Identifier(s):
- OSTI ID: 1702249
- Grant/Contract Number:
- AC02-06CH11357
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Acta Materialia
- Additional Journal Information:
- Journal Volume: 198; Journal ID: ISSN 1359-6454
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; irradiation effect; ion irradiation; in situ transmission electron microscopy; complex concentrated solid-solution alloy; cryogenic temperature
Citation Formats
Parkin, Calvin, Moorehead, Michael, Elbakhshwan, Mohamed, Hu, Jing, Chen, Wei-Ying, Li, Meimei, He, Lingfeng, Sridharan, Kumar, and Couet, Adrien. In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation. United States: N. p., 2020.
Web. doi:10.1016/j.actamat.2020.07.066.
Parkin, Calvin, Moorehead, Michael, Elbakhshwan, Mohamed, Hu, Jing, Chen, Wei-Ying, Li, Meimei, He, Lingfeng, Sridharan, Kumar, & Couet, Adrien. In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation. United States. https://doi.org/10.1016/j.actamat.2020.07.066
Parkin, Calvin, Moorehead, Michael, Elbakhshwan, Mohamed, Hu, Jing, Chen, Wei-Ying, Li, Meimei, He, Lingfeng, Sridharan, Kumar, and Couet, Adrien. Sat .
"In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation". United States. https://doi.org/10.1016/j.actamat.2020.07.066. https://www.osti.gov/servlets/purl/1776842.
@article{osti_1776842,
title = {In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation},
author = {Parkin, Calvin and Moorehead, Michael and Elbakhshwan, Mohamed and Hu, Jing and Chen, Wei-Ying and Li, Meimei and He, Lingfeng and Sridharan, Kumar and Couet, Adrien},
abstractNote = {This study characterizes the microstructural evolution of single-phase complex concentrated solid-solution alloy (CSA) compositions under heavy ion irradiation with the goal of evaluating mechanisms for CSA radiation tolerance in advanced fission systems. Three such alloys, Cr18Fe27Mn27Ni 28, Cr15Fe35Mn15Ni35, and equimolar NbTaTiV, along with reference materials (pure Ni and E90 for the Cr-FeMnNi family and pure V for NbTaTiV) were irradiated at 50 K and 773 K with 1 MeV Kr++ ions to various levels of displacements per atom (dpa) using in-situ transmission electron microscopy. Cryogenic irradiation resulted in small defect clusters and faulted dislocation loops as large as 12 nm in face-centered cubic (FCC) CSAs. With thermal diffusion suppressed at cryogenic temperatures, defect densities were lower in all CSAs than in their less compositionally complex reference materials indicating that point defect production is reduced during the displacement cascade stage. High temperature irradiation of the two FCC CSA resulted in the formation of interstitial dislocation loops which by 2 dpa grew to an average size of 27 nm in Cr18Fe27Mn27Ni28 and 10 nm in Cr15Fe35Mn15Ni35. This difference in loop growth kinetics was attributed to the difference in Mn-content due to its effect on the nucleation rate by increasing vacancy mobility or reducing the stacking-fault energy.},
doi = {10.1016/j.actamat.2020.07.066},
journal = {Acta Materialia},
number = ,
volume = 198,
place = {United States},
year = {Sat Aug 01 00:00:00 EDT 2020},
month = {Sat Aug 01 00:00:00 EDT 2020}
}
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