Development of real-time plasma current profile reconstruction with POINT diagnostic for EAST plasma control

Abstract This paper describes the plasma current profile reconstruction algorithms using POlarimeter-INTerferometer(POINT) measurements in GPU parallel equilibrium reconstruction code P-EFIT for EAST plasma control. Real-time POINT diagnostic data acquisition system is designed to satisfy the requirement for real-time reconstruction. The static time-slice and experimental simulation benchmark calculations using experimental magnetic plus POINT data of EAST discharge are conducted, which show that P-EFIT could provide reasonable plasma current and q profile in 0.7 ms in real-time with 65 × 65 spatial grid resolution. These results show that P-EFIT with POINT diagnostic could provide equilibrium reconstruction results for real-time plasma current and q profile control which will be applied in the near future.

[1]  L. Giannone,et al.  A Parallel Grad-Shafranov Solver for Real-Time Control of Tokamak Plasmas , 2012 .

[2]  R. J. Groebner,et al.  Scaling studies of the high mode pedestal , 1998 .

[3]  Kazuaki Hanada,et al.  Internal magnetic field measurements by laser-based POlarimeter-INTerferometer (POINT) system on EAST , 2016 .

[4]  L. L. Lao,et al.  EAST equilibrium current profile reconstruction using polarimeter-interferometer internal measurement constraints , 2017 .

[5]  L. L. Lao,et al.  Algorithm Validation of the Current Profile Reconstruction of EAST Based on Polarimeter/Interferometer , 2015 .

[6]  L. L. Lao,et al.  Real time equilibrium reconstruction for tokamak discharge control , 1998 .

[7]  Qiping Yuan,et al.  Implementation of GPU parallel equilibrium reconstruction for plasma control in EAST , 2016 .

[8]  Yong Guo,et al.  Fast equilibrium reconstruction for tokamak discharge control based on GPU , 2013 .

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

[10]  H. Q. Liu,et al.  Faraday-effect polarimeter-interferometer system for current density measurement on EAST. , 2014, The Review of scientific instruments.

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

[12]  L. L. Lao,et al.  High spatial resolution equilibrium reconstruction , 2011 .

[13]  C. Kessel,et al.  Control of plasma profiles in DIII-D discharges , 2006 .

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

[15]  Yasunori Kawano,et al.  A new approach of equilibrium reconstruction for ITER , 2011 .

[16]  L. Lao,et al.  MHD Equilibrium Reconstruction in the DIII-D Tokamak , 2005 .

[17]  Control of sawtooth via ECRH on EAST tokamak , 2016 .

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

[19]  Henrik Bindslev,et al.  Chapter 7: Diagnostics , 2007 .

[20]  Y. Nagayama,et al.  ECE IMAGE RECONSTRUCTION OF PARTIAL SAWTOOTH CRASHES IN OHMIC PLASMAS , 1996 .

[21]  J. Contributors,et al.  Accuracy of EFIT equilibrium reconstruction with internal diagnostic information at JET. , 2008, The Review of scientific instruments.