Effect of Carbon on Dislocation Loops Formation during Self-Ion Irradiation in Fe-Cr Alloys at High Temperatures
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- Tiantian Shi
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
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- Wenbo Liu
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
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- Zhengxiong Su
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
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- Xu Yan
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
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- Chenyang Lu
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
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- Di Yun
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
説明
<jats:p>In this study, two types of ferritic model alloys (Fe-9Cr and Fe-9Cr-C) were simultaneously irradiated with 3.5 MeV Fe13+ ions at 450 °C and 550 °C to a dose of 3dpa at the peak damage region, respectively. Transmission electron microscopy (TEM) was used to investigate the microstructural evolution of the Fe-Cr alloys after irradiation. The experimental results showed that the size of the dislocation loops formed in the Fe-9Cr-C alloy was larger than that in the Fe-9Cr alloy, but the loop density of the Fe-9Cr-C alloy was lower than that of the Fe-9Cr alloy after irradiation at 450 °C. The reason for this phenomenon was attributed to the fact that loops formed in Fe-9Cr-C alloy have greater capture efficiency for interstitial atoms. Compared to Fe-Cr alloys irradiated at 450 °C, high-density loops were not observed in the Fe-Cr alloys irradiated at 550 °C; the number of dislocation loops in the Fe-Cr alloys irradiated at 550 °C significantly decreased due to the rapid conversion of the dislocation loops into network dislocations. In addition, subgrains were observed in the Fe-Cr alloys after irradiation. The underlying reason behind the formation of subgrains is discussed in detail.</jats:p>
収録刊行物
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- Materials
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Materials 15 (6), 2211-, 2022-03-17
MDPI AG