1. Conceptual design study of the K-DEMO magnet system.
- Author
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Kim, Keeman, Oh, Sangjun, Park, Jong Sung, Lee, Chulhee, Im, Kihak, Kim, Hyung Chan, Lee, Gyung-Su, Neilson, George, Brown, Thomas, Kessel, Charles, Titus, Peter, and Zhai, Yuhu
- Subjects
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NUCLEAR fusion , *TRITIUM , *STEADY-state flow , *CONCEPTUAL design , *MAGNETS - Abstract
As the ITER is being constructed, there is a growing anticipation for an earlier realization of fusion energy. A major design philosophy for the initiated conceptual design study for a steady-state Korean fusion demonstration reactor (K-DEMO) is engineering feasibility. A two-staged development plan is envisaged. K-DEMO is designed not only to demonstrate a net electricity generation and a self-sustained tritium cycle, but also to be used, in its initial stage, as a component test facility. Then, in its second stage, a major upgrade is carried out by replacing in-vessel components in order to show a net electricity generation on the order of 500 MWe. After a thorough 0-D system analysis, the major radius and minor radius are chosen to be 6.8 m and 2.1 m, respectively. In order to minimize wave deflection, a top-launch high frequency (>200 GHz) electron cyclotron current drive (ECCD) system will be the key system for the current profile control. For matching the high frequency ECCD, a high toroidal field (TF) is required and can be achieved by using high current density Nb 3 Sn superconducting conductor. The peak magnetic field reaches to 16 T with the magnetic field at the plasma center above 7 T. Key features of the K-DEMO magnet system include the use of two TF coil winding packs, each of a different conductor design, to reduce the construction cost and save the space for the magnet structure material. [ABSTRACT FROM AUTHOR]
- Published
- 2015
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