Progress and improvement of KSTAR plasma control using model-based control simulators

Sang Hee Hahn, A. S. Welander, S. W. Yoon, J. G. Bak, N. W. Eidietis, H. S. Han, D. A. Humphreys, A. Hyatt, Y. M. Jeon, R. D. Johnson, H. S. Kim, J. Kim, E. Kolemen, D. Mueller, B. G. Penaflor, D. A. Piglowski, G. W. Shin, M. L. Walker, M. H. Woo

Research output: Contribution to journalArticlepeer-review

7 Scopus citations


Superconducting tokamaks like KSTAR, EAST and ITER need elaborate magnetic controls mainly due to either the demanding experiment schedule or tighter hardware limitations caused by the superconducting coils. In order to reduce the operation runtime requirements, two types of plasma simulators for the KSTAR plasma control system (PCS) have been developed for improving axisymmetric magnetic controls. The first one is an open-loop type, which can reproduce the control done in an old shot by loading the corresponding diagnostics data and PCS setup. The other one, a closed-loop simulator based on a linear nonrigid plasma model, is designed to simulate dynamic responses of the plasma equilibrium and plasma current (Ip) due to changes of the axisymmetric poloidal field (PF) coil currents, poloidal beta, and internal inductance. The closed-loop simulator is the one that actually can test and enable alteration of the feedback control setup for the next shot. The simulators have been used routinely in 2012 plasma campaign, and the experimental performances of the axisymmetric shape control algorithm are enhanced. Quality of the real-time EFIT has been enhanced by utilizations of the open-loop type. Using the closed-loop type, the decoupling scheme of the plasma current control and axisymmetric shape controls are verified through both the simulations and experiments. By combining with the relay feedback tuning algorithm, the improved controls helped to maintain the shape suitable for longer H-mode (10-16 s) with the number of required commissioning shots largely reduced.

Original languageEnglish (US)
Pages (from-to)542-547
Number of pages6
JournalFusion Engineering and Design
Issue number5
StatePublished - May 2014

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • General Materials Science
  • Mechanical Engineering


  • Control design
  • Magnetic fusion
  • Plasma control
  • Simulator
  • Tokamak


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