Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors

Nuclear Fushion

article

Xiaogang Liu¹  Fan Wu¹  Zhaoliang Wang¹  Guoqiang Li¹  Xiaoju Liu¹  Hang Li¹  Junjun Li¹  Yong Ren¹  Yu Wu¹  Xiang Gao¹ 

[1] Institute of Plasma Physics, Chinese Academy of Sciences;University of Science and Technology of China

关键词: tokamak;    DEMO;    superconducting magnet;    TF;    cable-in-conduit conductor;    electromagnetic load;    mechanicalanalysis.;   

DOI  :  10.1088/1741-4326/ab742d

来源: Institute of Physics Publishing Ltd.

【 摘 要 】

A comprehensive research facility project was approved in December 2018 with funding of 345 million EUR, to support the research and development of the China Fusion Engineering Test Reactor (CFETR). As part of this project, a full-size CFETR toroidal field (TF) coil will be designed, manufactured and tested by the Institute of Plasma Physics Chinese Academy of Sciences. Two options are being explored in parallel for the TF coil design, using either circle-in-square or rectangular cable-in-conduit conductors (CICCs). The rectangular CICC has been reported to have some merits for a DEMO TF coil, as reported in designs of the EU-DEMO and K-DEMO. First this paper presents the progress in the conceptual design of the CFETR TF coil with rectangular CICCs, according to the most recent reference single-null configuration and radial build of CFETR. Then, electromagnetic analyses are performed to give the magnetic field distributions, toroidal field ripple, in-plane and out-of-plane Lorentz loads. Finally, 3D global and 2D local mechanical analyses are conducted, and the detailed mechanical behavior of the TF coil is illustrated and discussed. Our analyses indicate that the present TF design is reasonable, considering the ITER criteria, and provides valuable insight into the mechanical behavior of the CFETR TF coil system.

【 授权许可】

Unknown