2012
DOI: 10.1109/tps.2011.2181958
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Key Features in the Operation of KSTAR

Abstract: The Korea Superconducting Tokamak Advanced Research (KSTAR) device is aimed at advanced tokamak (AT) research. Three years have passed since it achieved its first plasma in 2008. Because it is a superconducting machine and is working toward AT research, it has unique features in terms of the machine engineering and operation. The toroidal field (TF) magnet coils are made of Nb 3 Sn, which provide high TFs up to 3.5 T, and have been fully tested. The poloidal field (PF) magnet coils, consisting of both Nb 3 Sn … Show more

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Cited by 7 publications
(3 citation statements)
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“…One of the main research missions of KSTAR along the path to the commercialization of the fusion energy is to develop and exploit the steady-state and advanced operation scenarios. In these scenarios the information on the current density profiles is critical to assess the external current drive into the plasma and the bootstrap current formed near the edge pedestal during highconfinement modes of operation [5]. Therefore, current profile measurements for both the core and edge region of the plasma should be made.…”
Section: Jinst 8 C10022mentioning
confidence: 99%
“…One of the main research missions of KSTAR along the path to the commercialization of the fusion energy is to develop and exploit the steady-state and advanced operation scenarios. In these scenarios the information on the current density profiles is critical to assess the external current drive into the plasma and the bootstrap current formed near the edge pedestal during highconfinement modes of operation [5]. Therefore, current profile measurements for both the core and edge region of the plasma should be made.…”
Section: Jinst 8 C10022mentioning
confidence: 99%
“…Its algorithm is computationally intensive such that it cannot be used directly for real-time discharge control. To compute discharge parameters in real time rapidly enough for tokamak feedback control, simpler algorithms implemented at most tokamak facilities [3][4][5][6][7][8][9][10][11] approximate the results of the full equilibrium reconstruction. For example, the P-EFIT has been used on EAST, which can complete a magnetic equilibrium reconstruction iteration in 300 μs with 65×65 grids.…”
Section: Introductionmentioning
confidence: 99%
“…In [4], a real-time version of EFIT is described through modifying some algorithms and it could provide a converged equilibrium result in about 30 ms with a 33 × 33 grid. The real-time-EFIT (RT-EFIT) [5] is another real-time version of EFIT which is currently used by DIII-D, KSTAR, NSTX, MAST and EAST [5][6][7][8][9]. The RT-EFIT code made many simplifications and the spatial resolution is relatively low compared with the off-line EFIT.…”
Section: Introductionmentioning
confidence: 99%