2005
DOI: 10.1088/0029-5515/45/8/003
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Status of the KSTAR superconducting magnet system development

Abstract: The aim of the Korea superconducting tokamak advanced research (KSTAR) project is to develop a steady-state-capable advanced superconducting tokamak for establishing a scientific and technological basis for an attractive fusion reactor. Since the KSTAR mission includes the achievement of a steady-state-capable operation, the use of superconducting coils is an obvious choice for the magnet system. The KSTAR superconducting magnet system consists of 16 toroidal field (TF) and 14 poloidal field (PF) coils which i… Show more

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Cited by 41 publications
(16 citation statements)
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(13 reference statements)
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“…This technology has been used successfully in model coils and in smaller fusion experiments. In fact, all superconducting fusion systems in operation or under construction (EAST, KSTAR, SST-1, LHD PF coils, Wendelstein 7-X, ITER) [14][15][16][17][18] use the Cable-in-Conduit-Conductor technology invented and developed in the US in the 1970s [19]. Magnet design for fusion applications requires multidisciplinary engineering skills including applied superconductivity, mechanical engineering, electrical engineering, materials science, and engineering design.…”
Section: Background On Fusion Magnetsmentioning
confidence: 99%
“…This technology has been used successfully in model coils and in smaller fusion experiments. In fact, all superconducting fusion systems in operation or under construction (EAST, KSTAR, SST-1, LHD PF coils, Wendelstein 7-X, ITER) [14][15][16][17][18] use the Cable-in-Conduit-Conductor technology invented and developed in the US in the 1970s [19]. Magnet design for fusion applications requires multidisciplinary engineering skills including applied superconductivity, mechanical engineering, electrical engineering, materials science, and engineering design.…”
Section: Background On Fusion Magnetsmentioning
confidence: 99%
“…The conductor was fabricated by wrapping the 2.86 mm thickness Incoloy908 strip around 324 Nb 3 Sn strands and 162 copper strands. The heat treatment of Each Nb 3 Sn coil winding pack in vacuum furnace has accomplished for about 6 weeks at 660 • C. Any severe defect was not found such as strain accelerated grain boundary oxidation [5]. To give an electrical insulation, each turn was wrapped with S-glass and finally impregnated with epoxy.…”
Section: Superconducting Magnet Systemmentioning
confidence: 99%
“…A 12 T Nb 3 Sn coil was successfully built and tested in Japan in 1985 15) and the Nb 3 Sn-based Korean Superconducting Tokamak Advanced Research (KSTAR) 16) , is just now being completed. The International Thermonuclear Experimental Reactor (ITER) is now underway and will be used as the primary example in the comparison of magnet technologies 17) .…”
Section: Fusion Magnetsmentioning
confidence: 99%