L. Bromberg1, T. Brown2, F. Dahlgren2, P. Heitzenroeder2
1MIT Plasma Science and Fusion Center, USA
2Princeton Plasma Physics Laboratory, Princeton, NJ, USA
Tóm tắt
This paper presents a conceptual design of the magnet systems for an advanced tokamak fusion reactor (ARIES-AT). The main emphasis of the paper is the extrapolation of the current state-of-the-art in high temperature superconductors and coil design, and their implementation in an advanced commercial fusion reactor concept. A conceptual design of both the poloidal field coils and toroidal field coils is presented. The current design point is described and supported with a preliminary structural analysis and a discussion of the merits, performance, and economics of high temperature vs. low temperature superconductors in an advanced fusion reactor design.
Từ khóa
#Fusion reactor design #Superconducting coils #Superconducting magnets #High temperature superconductors #Toroidal magnetic fields #Plasma temperature #Fusion reactors #Leg #Shape #Nuclear and plasma sciencesTài liệu tham khảo
10.1016/0011-2275(94)90036-1
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