Author/Authors :
Xiao، نويسنده , , B.J. and Yuan، نويسنده , , Q.P. and Humphreys، نويسنده , , D.A. and Walker، نويسنده , , M.L. and Hyatt، نويسنده , , A.W. and Leuer، نويسنده , , J.A. and Jackson، نويسنده , , G.L. and Mueller، نويسنده , , D. and Penaflor، نويسنده , , B.G. and Pigrowski، نويسنده , , D.A. and Johnson، نويسنده , , R.D. and Welander، نويسنده , , A.S. and Zhang، نويسنده , , R.R. and Luo، نويسنده , , Z.P. and Guo، نويسنده , , Y. and Xing، نويسنده ,
Abstract :
In recent 2 years, various algorithms to control plasma shape, current and density have been implemented or improved for EAST tokamak. These plasma control performances have been verified by either simulated or actual experimental operation, and thus plasma control basis has been established for the long pulse operation and high performance H-mode plasma operation with low hybrid wave (LHW) and ion cyclotron resonance frequency (ICRF) heating. Startup simulation has been done by using TOKSYS code for the plasma breakdown in either 3.1 Wb or 4.5 Wb initial poloidal flux state and the scenarios proved to be robust and used for routine operation. Various shape configurations have been well feedback controlled by using ISOFLUX limited, double-null or single null algorithms based on RTEFIT equilibrium reconstruction. For the long pulse operation, strike point control and magnetics drift compensation have been implemented in the plasma control system (PCS). To improve the operation safety and efficiency, the verification of magnetic diagnostics before plasma breakdown has been demonstrated adequate to prevent a discharge in case of key sensor failure.
