Microstructural evolution of a silicon carbide-carbon coated nanostructured ferritic alloy composite during in-situ Kr ion irradiation at 300°C 450°C

被引:5
作者
Bawane, Kaustubh [1 ]
Lu, Kathy [1 ]
Bai, Xian-Ming [1 ]
Hu, Jing [2 ]
Li, Meimei [2 ]
Baldo, Peter M. [2 ]
Ryan, Edward [2 ]
机构
[1] Virginia Tech, Dept Mat Sci & Engn, Blacksburg, VA 24061 USA
[2] Argonne Natl Lab, IVEM Tandem Facil, Lemont, IL USA
来源
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY | 2021年 / 71卷
关键词
In-situ ion irradiation; Ferritic steel; (FeCr)(7)C-3; Metal matrix composite; Fuel cladding; TRANSMISSION ELECTRON-MICROSCOPY; DISLOCATION LOOPS; DAMAGE EVOLUTION; RADIATION-DAMAGE; THIN-FOILS; FE; PRECIPITATION; RESISTANCE; OXIDATION; FISSION;
D O I
10.1016/j.jmst.2020.07.025
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
This work focuses on irradiation behaviors of a novel silicon carbide and carbon coated nanostructured ferritic alloy (SiC-C@NFA) composite for potential applications as a cladding and structural material for next generation nuclear reactors. The SiC-C@NFA samples were irradiated with 1 MeV Kr ions up to 10 dpa at 300 and 450 degrees C. Microstructures and defect evolution were studied in-situ at the IVEM-Tandem facility at Argonne National Laboratory. The effects of ion irradiation on various phases such as alpha-ferrite matrix, (Fe,Cr)(7)C-3, and (Ti, W)C precipitates were evaluated. The alpha-ferrite matrix showed a continuous increase in dislocation density along with spatial ordering of dislocation loops (or loop strings) at >5 dpa. The size of the dislocation loops at 450 degrees C was larger than that at 300 degrees C. The nucleation and growth of new (Ti, W)C precipitates in alpha-ferrite grains were enhanced with the ion dose at 450 degrees C. This study provides new insight into the irradiation resistance of the SiC-C@NFA system. (C) 2021 Published by Elsevier Ltd on behalf of The editorial office of Journal of Materials Science & Technology.
引用
收藏
页码:75 / 83
页数:9
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