Overview of the Design Status of the Superconducting Magnet System of the CFETR
| Autor: | Jinggang Qin, Jinxing Zheng, Kun Lu, Yuntao Song, Xufeng Liu |
|---|---|
| Rok vydání: | 2018 |
| Předmět: |
Superconductivity
Physics Nuclear engineering Solenoid Superconducting magnet Plasma Fusion power Condensed Matter Physics 01 natural sciences 010305 fluids & plasmas Electronic Optical and Magnetic Materials Conductor Magnet 0103 physical sciences Electrical and Electronic Engineering 010306 general physics Electrical conductor |
| Zdroj: | IEEE Transactions on Applied Superconductivity. 28:1-5 |
| ISSN: | 2378-7074 1051-8223 |
| Popis: | The concept design of the China Fusion Engineering Test Reactor (CFETR) was started in 2012 in two stages. For CFETR-Phase I, the major radius is 5.7 m, the minor radius is 1.6 m, and the magnetic field at the plasma region, BT , is 4–5 T. There were 16 toroidal field coils and six central solenoid coils designed by a Nb3Sn cable-in-conduit conductor (CICC) with the maximum operation current of 64 and 50 kA, respectively. Three types of plasma equilibrium configuration (ITER-like single null, super-X, and snowflake) were designed. The maximum flux provided by the central solenoid is set at 180 V⋅s. However, to get much higher operation parameters such as steady-state operation, particle and heat exhaust, disruption mitigation and avoidance, ELM control, and material damage by high heat flux and neutron, the superconducting magnet system of CFETR-phase II has been updated based on the larger machine with R = 6.7 m−7.0 m, a = 2.0 m, and BT = 6.5–7 T. Such a new design makes over 1-GW fusion power and better plasma performance possible. Hybrid TF coils are designed by a high-performance Nb3Sn conductor, since the maximum magnetic field can reach to 14–15 T. Besides, in order to save the space for the blanket system and get higher flux, a high-temperature superconducting Bi-2212 magnet with better current-carrying performance under high field is supposed to be employed for the CS coils of CFETR-phase II. The Bi-2212 CICC sample has been tested at 4.2 K with a critical current of 26.6 kA under its self-field. |
| Databáze: | OpenAIRE |
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