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1. Design and construction of the KSTAR tokamak

Author

G.S. Lee, M. Kwon, C.J. Doh, B.G. Hong, K. Kim, M.H. Cho, W. Namkung, C.S. Chang, Y.C. Kim, J.Y. Kim, H.G. Jhang, D.K. Lee, K.I. You, J.H. Han, M.C. Kyum, J.W. Choi, J. Hong, W.C. Kim, B.C. Kim, J.H. Choi, S.H. Seo, H.K. Na, H.G. Lee, S.G. Lee, S.J. Yoo, B.J. Lee, Y.S. Jung, J.G. Bak, H.L. Yang, S.Y. Cho, K.H. Im, N.I. Hur, I.K. Yoo, J.W. Sa, K.H. Hong, G.H. Kim, B.J. Yoo, H.C. Ri, Y.K. Oh, Y.S. Kim, C.H. Choi, D.L. Kim, Y.M. Park, K.W. Cho, T.H. Ha, S.M. Hwang, Y.J. Kim, S. Baang, S.I. Lee, H.Y. Chang, W. Choe, S.G. Jeong, S.S. Oh, H.J. Lee, B.H. Oh, B.H. Choi, C.K. Hwang, S.R. In, S.H. Jeong, I.S. Ko, Y.S. Bae, H.S. Kang, J.B. Kim, H.J. Ahn, D.S. Kim, J.H. Lee, Y.W. Lee, Y.S. Hwang, S.H. Hong, K.-H. Chung, D.-I. Choi, and KSTAR Team

Subjects
Nuclear and High Energy Physics, Electric power system, Tokamak, law, Nuclear engineering, KSTAR, Plasma shaping, Divertor, Water cooling, Plasma diagnostics, Superconducting magnet, Condensed Matter Physics, law.invention
Abstract

The extensive design effort for KSTAR has been focused on two major aspects of the KSTAR project mission - steady-state-operation capability and advanced tokamak physics. The steady state aspect of the mission is reflected in the choice of superconducting magnets, provision of actively cooled in-vessel components, and long pulse current drive and heating systems. The advanced tokamak aspect of the mission is incorporated in the design features associated with flexible plasma shaping, double null divertor and passive stabilizers, internal control coils and a comprehensive set of diagnostics. Substantial progress in engineering has been made on superconducting magnets, the vacuum vessel, plasma facing components and power supplies. The new KSTAR experimental facility with cryogenic system and deionized water cooling and main power systems has been designed, and the construction work is under way for completion in 2004.

Published
2001
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2. The KSTAR project: An advanced steady state superconducting tokamak experiment

Author

G.S Lee, J Kim, S.M Hwang, C.S Chang, H.Y Chang, M.H Cho, B.H Choi, K Kim, K.W Cho, S Cho, K.K Choh, C.H Choi, J.H Choi, J.W Choi, I.S Choi, C.J Do, T.H Ha, J.H Han, J.S Hong, K.H Hong, N.I Hur, I.S Hwang, K.H Im, H.G Jhang, Y.S Jung, B.C Kim, D.L Kim, G.H Kim, H.S Kim, J.S Kim, J.Y Kim, W.C Kim, Y.S Kim, K.H Kwon, M.C Kyum, B.J Lee, D.K Lee, H.G Lee, J.M Lee, S.G Lee, H.G Na, Y.K Oh, J.H Park, H.C Ri, Y.S Ryoo, K.Y Song, H.L Yang, J.G Yang, B.J Yoo, S.J Yoo, N.S Yoon, S.B Yoon, G.H You, K.I You, W Choe, D.-I Choi, S.G Jeong, D.Y Lee, Y.S Bae, H.S Kang, G.N Kim, I.S Ko, W Namkung, J.S Oh, Y.D Bae, Y.S Cho, B.G Hong, G Hong, C.K Hwang, S.R In, M.H Ju, H.J Lee, B.H Oh, B.J Yoon, S Baang, H.J Choi, J Hwang, M.G Kim, Y.J Kim, S.I Lee, J Yee, C.S Yoon, K.-H Chung, S.H Hong, Y.S Hwang, S.H Kim, Y.H Kim, K.H Chung, J.Y Lim, D.W Ha, S.S Oh, K.S Ryu, Q.L Wang, T.K Ko, J Joo, S Suh, J.H Lee, Y.W Lee, H.S Shin, I.H Song, J Baek, I.Y Han, Y Koh, P.Y Park, C Ryu, J.J Cho, D.M Hwang, J.A Schmidt, H.K Park, G.H Neilson, W.T Reiersen, R.T Simmons, S Bernabei, F Dahlgren, L.R Grisham, S.C Jardin, C.E Kessel, J Manickam, S.S Medley, N Pomphrey, J.C Sinnis, T.G Brown, R.B White, K.M Young, J Schultz, P.W Wang, L Sevier, M.D Carter, P.M Ryan, D.W Swain, D.N Hill, W.M Nevins, and B.J Braams

Subjects
Physics, Nuclear and High Energy Physics, Tokamak, Divertor, Nuclear engineering, Cyclotron, Pulse duration, Plasma, Fusion power, Condensed Matter Physics, law.invention, Nuclear magnetic resonance, law, Magnet, KSTAR
Abstract

The Korea Superconducting Tokamak Advanced Research (KSTAR) project is the major effort of the national fusion programme of the Republic of Korea. Its aim is to develop a steady state capable advanced superconducting tokamak to establish a scientific and technological basis for an attractive fusion reactor. The major parameters of the tokamak are: major radius 1.8 m, minor radius 0.5 m, toroidal field 3.5 T and plasma current 2 MA, with a strongly shaped plasma cross-section and double null divertor. The initial pulse length provided by the poloidal magnet system is 20 s, but the pulse length can be increased to 300 s through non-inductive current drive. The plasma heating and current drive system consists of neutral beams, ion cyclotron waves, lower hybrid waves and electron cyclotron waves for flexible profile control in advanced tokamak operating modes. A comprehensive set of diagnostics is planned for plasma control, performance evaluation and physics understanding. The project has completed its conceptual design and moved to the engineering design and construction phase. The target date for the first plasma is 2002.

Published
2000
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