کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
7962953 | 1514137 | 2018 | 17 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Microstructural evolution of NF709 austenitic stainless steel under in-situ ion irradiations at room temperature, 300, 400, 500 and 600â¯Â°C
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موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
انرژی هسته ای و مهندسی
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چکیده انگلیسی
Irradiation induced microstructural changes in the NF709 austenitic stainless steel were investigated under 1â¯MeV Kr ion irradiations to a dose of 3â¯dpa at room temperature (RT), 300, 400, 500 and 600â¯Â°C, and a dose of 20â¯dpa at RT. The irradiation-induced defects and the stability of precipitates were characterized with transmission electron microscopy (TEM). Frank dislocation loops were observed in all the irradiated samples, and the loop sizes were much larger at 600â¯Â°C than those at lower temperatures. “Raft” defect structures, formed through self-alignment of small dislocation loops, were also observed in all irradiated samples. M23C6 precipitates were amorphorized under irradiations at RT and 300â¯Â°C, but remained to be crystalline at 400â¯Â°C and above. MX precipitates were stable under irradiations at RT up to 20 dpa, and at temperatures below 600â¯Â°C to 3 dpa. At 600â¯Â°C, some MX precipitates were observed to dissolve during in-situ irradiation, suggesting possible precipitate instability at this irradiation temperature.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 509, October 2018, Pages 644-653
Journal: Journal of Nuclear Materials - Volume 509, October 2018, Pages 644-653
نویسندگان
Chi Xu, Wei-Ying Chen, Yiren Chen, Yong Yang,