Kim, Keeman
(National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, Republic of Korea)
,
Oh, Sangjun
(National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, Republic of Korea)
,
Park, Jong Sung
(National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, Republic of Korea)
,
Lee, Chulhee
(National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, Republic of Korea)
,
Im, Kihak
(National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, Republic of Korea)
,
Kim, Hyung Chan
(National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, Republic of Korea)
,
Lee, Gyung-Su
(National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, Republic of Korea)
,
Neilson, George
(Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA)
,
Brown, Thomas
(Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA)
,
Kessel, Charles
(Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA)
,
Titus, Peter
(Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA)
,
Zhai, Yuhu
(Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA)
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 develo...
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 500MWe. After a thorough 0-D system analysis, the major radius and minor radius are chosen to be 6.8m and 2.1m, respectively. In order to minimize wave deflection, a top-launch high frequency (>200GHz) 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 Nb3Sn superconducting conductor. The peak magnetic field reaches to 16T with the magnetic field at the plasma center above 7T. 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. Highlights Perform a preliminary conceptual study for a steady-state Korean DEMO reactor. Present a preliminary design of TF (toroidal field) magnet. Present a preliminary design of CS (central solenoid) magnet. Present a preliminary design of PF (toroidal field) magnet.
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 500MWe. After a thorough 0-D system analysis, the major radius and minor radius are chosen to be 6.8m and 2.1m, respectively. In order to minimize wave deflection, a top-launch high frequency (>200GHz) 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 Nb3Sn superconducting conductor. The peak magnetic field reaches to 16T with the magnetic field at the plasma center above 7T. 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. Highlights Perform a preliminary conceptual study for a steady-state Korean DEMO reactor. Present a preliminary design of TF (toroidal field) magnet. Present a preliminary design of CS (central solenoid) magnet. Present a preliminary design of PF (toroidal field) magnet.
IEEE Trans. Appl. Supercond. Oh 19 1557 2009 10.1109/TASC.2009.2018787 Design and thermo-hydaulic stability analysis of PUMA upgrade for the development of a test facility of superconducting CICCs
J. Appl. Phys. Oh 99 033909 2006 10.1063/1.2170415 A scaling law for the critical current of Nb3Sn strands based on strong-coupling theory of superconductivity
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