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Equilibrium and global MHD stability study of KSTAR high beta plasmas under passive and active mode control SCIE SCOPUS

Title
Equilibrium and global MHD stability study of KSTAR high beta plasmas under passive and active mode control
Authors
Katsuro-Hopkins, OSabbagh, SABialek, JMPark, HKBak, JGChung, JHahn, SHKim, JYKwon, MLee, SGYoon, SWYou, KIGlasser, AHLao, LL
Date Issued
2010-02
Publisher
INT ATOMIC ENERGY AGENCY
Abstract
The Korea Superconducting Tokamak Advanced Research, KSTAR, is designed to operate a steady-state, high beta plasma while retaining global magnetohydrodynamic (MHD) stability to establish the scientific and technological basis of an economically attractive fusion reactor. An equilibrium model is established for stability analysis of KSTAR. Reconstructions were performed for the experimental start-up scenario and experimental first plasma operation using the EFIT code. The VALEN code was used to determine the vacuum vessel current distribution. Theoretical high beta equilibria spanning the expected operational range are computed for various profiles including generic L-mode and DIII-D experimental H-mode pressure profiles. Ideal MHD stability calculations of toroidal mode number of unity using the DCON code shows a factor of 2 improvement in the wall-stabilized plasma beta limit at moderate to low plasma internal inductance. The planned stabilization system in KSTAR comprises passive stabilizing plates and actively cooled in-vessel control coils (IVCCs) designed for non-axisymmetric field error correction and stabilization of slow timescale MHD modes including resistive wall modes (RWMs). VALEN analysis using standard proportional gain shows that active stabilization near the ideal wall limit can be reached with feedback using the midplane segment of the IVCC. The RMS power required for control using both white noise and noise taken from NSTX active stabilization experiments is computed for beta near the ideal wall limit. Advanced state-space control algorithms yield a factor of 2 power reduction assuming white noise while remaining robust with respect to variations in plasma beta.
Keywords
RESISTIVE WALL MODE; DIII-D; FEEDBACK; TOKAMAK; STABILIZATION; DESIGN; NSTX; ITER
URI
https://oasis.postech.ac.kr/handle/2014.oak/26421
DOI
10.1088/0029-5515/50/2/025019
ISSN
0029-5515
Article Type
Article
Citation
NUCLEAR FUSION, vol. 50, no. 2, 2010-02
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