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

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.

[1]  J. Manickam,et al.  Advances in global MHD mode stabilization research on NSTX , 2010 .

[2]  Gerald A. Navratil,et al.  Enhanced ITER resistive wall mode feedback performance using optimal control techniques , 2007 .

[3]  K. Tritz,et al.  Active stabilization of the resistive-wall mode in high-beta, low-rotation plasmas. , 2006, Physical review letters.

[4]  L. L. Lao,et al.  Resistive wall stabilized operation in rotating high beta NSTX plasmas , 2006 .

[5]  M. Mauel,et al.  Suppression of rotating external kink instabilities using optimized mode control feedback , 2005 .

[6]  J. B. Lister,et al.  Feedback and rotational stabilization of resistive wall modes in ITER , 2005 .

[7]  L. L. Lao,et al.  Resistive wall mode stabilization with internal feedback coils in DIII-D , 2004 .

[8]  L. L. Lao,et al.  Equilibrium properties of spherical torus plasmas in NSTX , 2001 .

[9]  Yong-Seok Hwang,et al.  Design and construction of the KSTAR tokamak , 2001 .

[10]  Gerald A. Navratil,et al.  Modeling of active control of external magnetohydrodynamic instabilities , 2001 .

[11]  Michio Okabayashi,et al.  ACTIVE FEEDBACK STABILZATION OF THE RESISTIVE WALL MODE ON THE DIII-D DEVICE , 2000 .

[12]  Tetsuya Sato,et al.  Non-linear simulations of internal reconnection events in spherical tokamaks , 2000 .

[13]  J. H. Schultz,et al.  The design of the KSTAR tokamak , 1999 .

[14]  J. H. Schultz,et al.  The KSTAR project: An advanced steady state superconducting tokamak experiment , 2000 .

[15]  R. D. Stambaugh,et al.  THE SPHERICAL TOKAMAK PATH TO FUSION POWER , 1998 .

[16]  Lao,et al.  High internal inductance improved confinement H-mode discharges obtained with an elongation ramp technique in the DIII-D tokamak. , 1993, Physical review letters.

[17]  Bell,et al.  Bootstrap current in TFTR. , 1988, Physical review letters.

[18]  Bernard Friedland,et al.  Control System Design: An Introduction to State-Space Methods , 1987 .

[19]  L. Lao,et al.  Reconstruction of current profile parameters and plasma shapes in tokamaks , 1985 .

[20]  B. Moore Principal component analysis in linear systems: Controllability, observability, and model reduction , 1981 .