Progress in engineering design of CFETR toroidal field superconducting magnet
China Fusion Engineering Test Reactor (CFETR) is a national scientific research project which is aimed to initially build fusion energy production up to 2×108 W and to eventually reach relevant power level 1×109 W of DEMO. The major and minor radius of CFETR are 7.2 m and 2.2 m, respectively. As one...
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Published in | Fusion engineering and design Vol. 177; p. 113063 |
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Main Authors | , , , , , , , , , , , |
Format | Journal Article |
Language | English |
Published |
Amsterdam
Elsevier B.V
01.04.2022
Elsevier Science Ltd |
Subjects | |
Online Access | Get full text |
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Summary: | China Fusion Engineering Test Reactor (CFETR) is a national scientific research project which is aimed to initially build fusion energy production up to 2×108 W and to eventually reach relevant power level 1×109 W of DEMO. The major and minor radius of CFETR are 7.2 m and 2.2 m, respectively. As one of the most important components, a full-sized CFETR Toroidal Field (TF) magnet was designed. The height and width of the TF magnet are 21.3 m and 12.4 m separately. To provide 6.5 T at plasma center, TF magnet operates at a current of 95,600 A/turn. In this paper, engineering design of TF coil case (TFCC) is firstly introduced. And the structural design of internal joints, external joints, conductor, and insulation system of TF winding pack (WP) is presented. Based on the thermal load, the cooling system is also designed. Finally, some auxiliary structures are designed to ensure the normal operation of TF magnet. |
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ISSN: | 0920-3796 1873-7196 |
DOI: | 10.1016/j.fusengdes.2022.113063 |