کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
7965738 | 1514182 | 2015 | 4 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Temperature impact on W surface exposed to He plasma in LHD and its consequences for the material properties
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موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
انرژی هسته ای و مهندسی
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چکیده انگلیسی
A new temperature controlled material probe was designed for the exposure of W samples to He plasma in the LHD (Large Helical Device). TEM (Transmission Electron Microscopy) analysis allowed the study of the impact of He irradiation under high temperatures (up to 600 °C) on W microstructure: bubbles and dislocation loops are formed at the surface. A heavily damaged layer rich in both damages is formed at the very surface layer whose thickness increases with the incident fluence; beyond this layer, bubbles are observed much deeper than expected, rising concerns about the consequences for the material properties conservation. Nano-indentation measurements showed that the hardness of exposed tungsten indeed increases as the dislocation loops are formed and large bubbles appear in the material.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 463, August 2015, Pages 316-319
Journal: Journal of Nuclear Materials - Volume 463, August 2015, Pages 316-319
نویسندگان
E. Bernard, R. Sakamoto, N. Yoshida, H. Yamada,