The KSTAR project: An advanced steady state superconducting tokamak experiment

被引:187
作者
Lee, GS [1 ]
Kim, J
Hwang, SM
Chang, CS
Chang, HY
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
机构
[1] Korea Basic Sci Inst, Natl Fus Res & Dev Ctr, Taejon, South Korea
[2] Korea Adv Inst Sci & Technol, Taejon 305701, South Korea
[3] Pohang Univ Sci & Technol, Pohang, South Korea
[4] Korea Atom Energy Res Inst, Taejon, South Korea
[5] Samsung Adv Inst Technol, Taejon, South Korea
[6] Seoul Natl Univ, Seoul, South Korea
[7] Korea Res Inst Stand & Sci, Taejon, South Korea
[8] Korea Electrotechnol Res Inst, Changwon, South Korea
[9] Yonsei Univ, Seoul 120749, South Korea
[10] Sungkyunkoan Univ, Seoul, South Korea
[11] POSCON Corp, Pohang, South Korea
[12] Dae Sung Cable Co, Seoul, South Korea
[13] Korea Iron Steel Wire Ltd, Seoul, South Korea
[14] CVE Corp, Seoul, South Korea
[15] Samsung Aerosp Corp, Changwon, South Korea
[16] Princeton Univ, Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[17] MIT, Cambridge, MA 02139 USA
[18] Gen Atom Co, San Diego, CA USA
[19] Oak Ridge Natl Lab, Oak Ridge, TN USA
[20] Univ Calif Lawrence Livermore Natl Lab, Livermore, CA USA
[21] NYU, New York, NY USA
关键词
D O I
10.1088/0029-5515/40/3Y/319
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
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.
引用
收藏
页码:575 / 582
页数:8
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