کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
4921050 | 1429332 | 2017 | 7 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Formation of snowflake diverted equilibria of CFETR
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کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
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چکیده انگلیسی
The Chinese Fusion Engineering Test Reactor (CFETR), a next-generation fully superconducting fusion reactor, is in the design stages. In this paper, we present three snowflake (SF) divertor configurations (SF+, exact SF, SFâ), to demonstrate the possibility of attaining these SF configurations with two special additional poloidal-field (PF) coils set on the CFETR, where all PF coils are outside the TF coils. Starting from a single null divertor (SND), a sequence of desirable SF configurations can be realized whereby the PF-coil currents are below the maximal design limits. Compared to the SND, the potential properties of these SFDs, including low-poloidal-field area, flux expansion, connection length, are analyzed and presented in this paper. As the required currents in some PF coils are higher for a SFD than a SND, an operating space of coil currents for the SFD was calculated at a range of the internal inductance (li) and flux states. The result indicates that though the current in CS1 PF coil limits access to the lower li and flux state region, the PF coils system can provide â¼30Â Wb for the flattop phase.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Fusion Engineering and Design - Volume 121, October 2017, Pages 117-123
Journal: Fusion Engineering and Design - Volume 121, October 2017, Pages 117-123
نویسندگان
H. Li, G.Q. Li, Z.P. Luo, D.M. Yao, Y. Guo, X. Gao,