IAEA Fusion Energy Conference 2010

Proceedings of the 23rd IAEA Fusion Energy Conference
Daejeon, 11-16 October 2010

Organized by the International Atomic Energy Agency
and hosted by the Government of the Republic of Korea

IAEA-CN-180

(FTP/P6-09) Status and Result of the KSTAR Upgrade for the 2010's Campaign

H.L. Yang1), Y.S. Kim1), Y.M. Park1), Y.S. Bae1), H.K. Kim1), K.M. Kim1), K.S. Lee1), H.T. Kim1), E.N. Bang1), M. Joung1), J.S. Kim1), W.S. Han1), S.I. Park2), J.H. Jeong2), H.J. Do2), H.J. Lee1), S.W. Kwag1), Y.B. Chang1), N.H. Song1), J.H. Choi1), D.K. Lee1), C.H. Kim1), J.K. Jin1), J.D. Kong1), S.L. Hong1), H.T. Park1), W. Namkung2), M.H. Cho2), H. Park2), J.G. Kwak3), D.H. Chang3), S.H. Jeong3), J.T. Jin3), S.R. In3), S.J. Wang3), S.H. Kim3), K. Watanabe4), L. Grisham5), M. Kwon1), Y. Gorelov6), J. Lohr6) and the KSTAR Team
 
1) National Fusion Research Institute, Daejeon, Republic of Korea
2) Pohang University of Science and Technology, Pohang, Republic of Korea
3) Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
4) Japan Atomic Energy Agency, 801-1, Mukoyama, Naka-shi, Ibaraki 311-0193, Japan
5) Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, NJ08543, USA
6) General Atomics, P.O. Box 85608, San Diego, CA92186-5608, USA

Abstract.  Because the 2010 operation of Korea Superconducting Tokamak Advanced Research (KSTAR) mainly aims to achieve strongly elongated and diverted plasma, all the necessary hardware systems to provide an essential circumstance for the plasma shaping were newly installed and upgraded in 2010. The hardware for the 2010 KSTAR operation comprises in-vessel components and power supplies for superconducting (SC) magnets. The in-vessel components, which contain limiters, divertor, passive stabilizer, in-vessel control coil (IVCC) system, have been upgraded with satisfactory performances. The SC magnet power supplies (MPS) also fully demonstrated their own designed functions during final commissioning for the 2010 operation. In addition to drastic upgrades of the in-vessel components and MPS, there were great progresses in the development of heating and current drive system including neutral beam injection (NBI), electron cyclotron current drive (ECCD), and lower hybrid current drive (LHCD) system to prepare an initial stage for steady-state operation. In this paper, general configuration of the upgraded systems described earlier will be outlined. Moreover, several key performances and test results of the systems will be also reported in summary.

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