The KSTAR project: An advanced steady state superconducting tokamak experiment

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Lee, GS / Kim, J / Hwang, SM / Chang, Choong-Seockresearcher / Chang, Hong-Youngresearcher / Cho, MH / Choi, BH / Kim, K / Cho, KW / Cho, S / Choh, KK / Choi, CH / Choi, JH / Choi, JW / Choi, IS / Do, CJ / Ha, TH / Han, JH / Hong, JS / Hong, KH / Hur, NI / Hwang, IS / Im, KH / Jhang, HG / Jung, YS / Kim, BC / Kim, DL / Kim, GH / Kim, HS / Kim, JS / Kim, JY / Kim, WC / Kim, YS / Kwon, KH / Kyum, MC / Lee, BJ / Lee, DK / Lee, HG / Lee, JM / Lee, SG / Na, HG / Oh, YK / Park, JH / Ri, HC / Ryoo, YS / Song, KY / Yang, HL / Yang, JG / Yoo, BJ / Yoo, SJ / Yoon, NS / Yoon, SB / You, GH / You, KI / Choe, Wonhoresearcher / Choi, Duk In / Jeong, Sangkwonresearcher / Lee, DY / Bae, YS / Kang, HS / Kim, GN / Namkung, W / Oh, JS / Bae, YD / Cho, YS / Hong, BG / Hong, G / Hwang, CK / In, SR / Ju, MH / Lee, HJ / Oh, BH / Yoon, BJ / Baang, S / Choi, HJ / Hwang, J / Kim, MG / Kim, YJ / Lee, SI / Yee, J / Yoon, CS / Chung, KH / Hong, SH / Hwang, YS / Kim, SH / Kim, YH / Chung, KH / Lim, JY / Ha, DW / Oh, SS / Ryu, KS / Wang, QL / Ko, TK / Joo, J / Suh, S / Choi, CH / Lee, JH / Lee, YW / Shin, HS / Song, IH / Baek, J / Han, IY / Koh, Y / Park, PY / Ryu, C / Cho, JJ / Hwang, DM / Kim, YS / Schmidt, JA / Park, HK / Neilson, GH / Reiersen, WT / Simmons, RT / Bernabei, S / Dahlgren, F / Grisham, LR / Jardin, SC / Kessel, CE / Manickam, J / Medley, SS / Pomphrey, N / Sinnis, JC / Brown, TG / White, RB / Young, KM / Schultz, J / Wang, PW / Sevier, L / Carter, MD / Ryan, PM / Swain, DW / Hill, DN / Nevins, WM / Braams, BJ
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 mi minor radius 0.5 m. toroidal held 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.
Publisher
INT ATOMIC ENERGY AGENCY
Issue Date
2000-03
Language
English
Article Type
Article; Proceedings Paper
Citation

NUCLEAR FUSION, v.40, pp.575 - 582

ISSN
0029-5515
URI
http://hdl.handle.net/10203/75933
Appears in Collection
PH-Journal Papers(저널논문)NE-Journal Papers(저널논문)ME-Journal Papers(저널논문)
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