کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
5454303 | 1514163 | 2017 | 25 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy
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کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
انرژی هسته ای و مهندسی
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![عکس صفحه اول مقاله: Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy](/preview/png/5454303.png)
چکیده انگلیسی
FeCrAl alloys are an attractive class of materials for nuclear power applications because of their increased environmental compatibility compared with more traditional nuclear materials. Preliminary studies into the radiation tolerance of FeCrAl alloys under accelerated neutron testing between 300 and 400 °C have shown post-irradiation microstructures containing dislocation loops and a Cr-rich αⲠphase. Although these initial studies established the post-irradiation microstructures, there was little to no focus on understanding the influence of pre-irradiation microstructures on this response. In this study, a well-annealed commercial FeCrAl alloy, Alkrothal 720, was neutron irradiated to 1.8 displacements per atom (dpa) at 382 °C and then the effect of random high-angle grain boundaries on the spatial distribution and size of aã100ã dislocation loops, a/2ã111ã dislocation loops, and black dot damage was analyzed using on-zone scanning transmission electron microscopy. Results showed a clear heterogeneous dislocation loop formation with a/2ã111ã dislocation loops showing an increased number density and size, black dot damage showing a significant number density decrease, and aã100ã dislocation loops exhibiting an increased size in the vicinity of the grain boundary. These results suggest the importance of the pre-irradiation microstructure and, specifically, defect sink density spacing to the radiation tolerance of FeCrAl alloys.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 483, January 2017, Pages 54-61
Journal: Journal of Nuclear Materials - Volume 483, January 2017, Pages 54-61
نویسندگان
Kevin G. Field, Samuel A. Briggs, Xunxiang Hu, Yukinori Yamamoto, Richard H. Howard, Kumar Sridharan,