Review of the Equilibrium Fitting for Non-Circular Tokamak

As the equilibrium fitting code (EFIT) is developing to perform the magnetic and the kinetic-magnetic analysis for tokamak device operation, it can be not only run in either the fitting mode or the equilibrium mode but also control operation of modern experimental fusion device. In this paper the history of EFIT code and its capabilities are described in section 2. A brief description of the off-line EFIT code and the development of the real-time EFIT (RTEFIT) code is shown in section 3 and 4 respectively. In the last section the summary of this paper is given.

[1]  S. Jardin,et al.  LETTER: Application of a new algorithm to plasma shape control in BPX , 1992 .

[2]  P. Mantica,et al.  Determination of equilibrium global parameters from external magnetic measurements in JET discharges with auxiliary heating , 1988 .

[3]  Didier Moreau,et al.  Plasma control issues for an advanced steady state tokamak reactor , 1999 .

[4]  N. Hosogane,et al.  Method for measuring divertor configuration parameters for feedback control in JT–60 , 1986 .

[5]  R. Miller,et al.  Flux surface shape and current profile optimization in tokamaks , 1977 .

[6]  J. Ferron,et al.  A high speed data acquisition and processing system for real time data analysis and control , 1992 .

[7]  G. Tonetti,et al.  Tokamak equilibrium reconstruction using Faraday rotation measurements , 1988 .

[8]  D. A. Humphreys,et al.  Control of plasma poloidal shape and position in the DIII-D tokamak , 1997, Proceedings of the 36th IEEE Conference on Decision and Control.

[9]  L. L. Lao,et al.  Equilibrium and stability studies for an iron core tokamak with a poloidal divertor , 1989 .

[10]  J. L. Luxon,et al.  Magnetic analysis of non-circular cross-section tokamaks , 1982 .

[11]  L. Lao,et al.  Variational moment solutions to the Grad–Shafranov equation , 1981 .

[12]  E. J. Strait,et al.  Real time analysis of tokamak discharge parameters , 1992 .

[13]  Vitalii D. Shafranov,et al.  Plasma equilibrium in a Tokamak , 1971 .

[14]  Ryuichi Shimada,et al.  JT-60 power supplies , 1987 .

[15]  C. A. Steed,et al.  CODAS: the JET control and data acquisition system , 1987 .

[16]  F. J. Helton,et al.  MHD equilibrium in non-circular tokamaks with field-shaping coil systems , 1978 .

[17]  L. L. Lao,et al.  Real time equilibrium reconstruction for control of the discharge in the DIII-D tokamak , 1997 .

[18]  N Singh,et al.  Computer experiments on the formation and dynamics of electric double layers , 1980 .

[19]  P. L. Mondino,et al.  The JET magnet power supplies and plasma control systems , 1987 .

[20]  Y. R. Martin,et al.  Feedback stabilization of axisymmetric modes in the TCV tokamak using active coils inside and outside the vacuum vessel , 1998 .

[21]  B. Braams,et al.  Fast determination of plasma parameters through function parametrization , 1986 .

[22]  G. R. Dyer,et al.  A model for coupled plasma current and position feedback control in the ISX-B tokamak , 1984 .

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

[24]  David W. Swain,et al.  An efficient technique for magnetic analysis of non-circular, high-beta tokamak equilibria , 1982 .

[25]  N. Fujisawa,et al.  Equilibrium and axisymmetric stability of dee-shaped plasmas in Doublet III , 1982 .

[26]  L. L. Lao,et al.  Separation of β̄p and ℓi in tokamaks of non-circular cross-section , 1985 .

[27]  M. Takahashi,et al.  JT-60 plasma control system , 1997 .

[28]  L. L. Lao,et al.  Equilibrium analysis of current profiles in tokamaks , 1990 .