DocumentCode :
3199175
Title :
Superconducting magnet power supply system for the KSTAR 1st plasma experiment and engineering
Author :
Choi, J.H. ; Kim, C.H. ; Lee, D.K. ; Kim, K.H. ; Ahn, H.S. ; Chu, Y. ; Kong, J.D. ; Hong, S.L. ; Jin, J.K. ; Hwang, I.S. ; Kim, Y.S. ; Park, J.S. ; Kwon, M. ; Ann, H.S. ; Jang, G.Y. ; Yun, M.S. ; Seong, D.K. ; Kim, Y.H. ; Lee, Y.W. ; Shin, H.S.
Author_Institution :
KSTAR Res. Center, Nat. Fusion Res. Inst. (NFRI ), Daejeon, South Korea
fYear :
2009
fDate :
1-5 June 2009
Firstpage :
1
Lastpage :
4
Abstract :
The Korea Superconducting Tokamak Advanced Research (KSTAR) device is an advanced superconducting tokamak to establish scientific and technological bases for an attractive fusion reactor. This device requires 3.5 Tesla of toroidal field (TF) for plasma confinement, and requires a strong poloidal flux swing to generate an inductive voltage to produce and sustain the tokamak plasma. KSTAR was originally designed to have 16 serially connected TF magnets for which the nominal current rating is 35.2 kA. KSTAR also has 7 pairs of poloidal field (PF) coils that are driven to 1 MA/sec for generation of the tokamak plasma according to the operation scenarios. The KSTAR Magnet Power Supply (MPS) was dedicated to the superconducting (SC) coil commissioning and 1st plasma experiment as a part of the system commissioning. This paper will describe key features of KSTAR MPS for the 1st plasma experiment, and will also report the engineering and commissioning results of the magnet power supplies.
Keywords :
Tokamak devices; fusion reactor design; fusion reactor operation; plasma toroidal confinement; superconducting coils; superconducting magnets; KSTAR design; KSTAR plasma experiment; Korea superconducting tokamak advanced research device; fusion reactor; magnet power supplies; magnetic flux density 3.5 tesla; plasma confinement; poloidal field coils; serially connected TF magnets; superconducting coil commissioning; superconducting magnet power supply system; toroidal field; Fusion power generation; Fusion reactor design; Fusion reactors; Plasma confinement; Plasma devices; Power supplies; Superconducting coils; Superconducting magnets; Tokamaks; Voltage; BRIS; Converter; KSTAR; MPS; PF; QP; TF; component;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
978-1-4244-2635-5
Electronic_ISBN :
978-1-4244-2636-2
Type :
conf
DOI :
10.1109/FUSION.2009.5226386
Filename :
5226386
Link To Document :
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