Abstract
To determine the engineering feasibility of an "inter-linked" (IL) superconducting central solenoid (CS) and poloidal field (PF) coil, we studied the basic engineering design of the IL-CS and PF coil. We were able to use IL superconducting coils in a tokamak fusion demonstration power plant (DEMO) reactor to achieve a sufficient amount of the CS magnetic flux swing for the current ramp-up while maintaining plasma size and also achieving an advanced divertor concepts of "super-X divertor (SXD)" by locating near the plasma. A basic idea of the IL superconducting CS and PF coil concept is to wind a CS (PF coil) such that it is linked in a set of toroidal field (TF) coils. In this study, we considered the conductor and feeder design of the IL-CS and PF coil including the superconducting strand type, cooling, and winding and assembly methods, and determined that react and wind Nb3Al is a candidate for use in an IL coil and feeder in this specification. This paper presents the preliminary engineering design results of the IL superconducting CS and PF coil for creating a SXD equilibrium configuration.
Original language | English |
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Pages (from-to) | 2456-2460 |
Number of pages | 5 |
Journal | Fusion Engineering and Design |
Volume | 89 |
Issue number | 9-10 |
DOIs | |
Publication status | Published - 2014 Oct |
Externally published | Yes |
Keywords
- Central solenoid
- Fusion reactor design
- Inter-linked
- Magnetic flux swing
- Super-X divertor
- Superconducting magnet
ASJC Scopus subject areas
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering