The EFIT program is integrated with the high resolution laser polarimeter interferometer system（POLARIS）, the soft X-ray imaging diagnostic system（SXR） and the electron cyclotron emission radiometer（ECE） in the ...The EFIT program is integrated with the high resolution laser polarimeter interferometer system（POLARIS）, the soft X-ray imaging diagnostic system（SXR） and the electron cyclotron emission radiometer（ECE） in the J-TEXT tokamak. Then some internal information about Faraday angle and the position of safety factor q=1 can be obtained as a constraint to EFIT. The modified EFIT code is used to calculate the internal parameters such as flux function, safety factor q, pressure and current density.展开更多
This paper introduces the design and implementation of an interactive tool, the EASTViewer, for the visualization of plasma equilibrium reconstruction results for EAST （the Experimental Advanced Superconducting Toka...This paper introduces the design and implementation of an interactive tool, the EASTViewer, for the visualization of plasma equilibrium reconstruction results for EAST （the Experimental Advanced Superconducting Tokamak）. Aimed at the operating system indepen- dently, Python, when combined with the PyGTK toolkit, is used as the programming language. Using modular design, the EASTViewer provides a unified interface with great flexibility. It is easy to access numerous data sources either from local data files or an MDSplus tree, and with the pre-defined configuration files, it can be extended to other tokamaks. The EASTViewer has been used as the major tool to visualize equilibrium data since the second EAST campaign in 2008, and it has been verified that the EASTViewer features a user-friendly interface, and has easy access to numerous data sources and cross-platforms.展开更多
Plasma equilibrium reconstruction provides essential information for tokamak operation and physical analysis.An extensive and reliable set of magnetic diagnostics is required to obtain accurate plasma equilibrium.This...Plasma equilibrium reconstruction provides essential information for tokamak operation and physical analysis.An extensive and reliable set of magnetic diagnostics is required to obtain accurate plasma equilibrium.This study designs and optimizes the magnetic diagnostics layout for the reconstruction of the equilibrium of the plasma according to the scientific objectives,engineering design parameters,and limitations of the Chinese Fusion Engineering Test Reactor(CFETR).Based on the CFETR discharge simulation,magnetic measurement data are employed to reconstruct consistent plasma equilibrium parameters,and magnetic diagnostics'number and position are optimized by truncated Singular value decomposition,verifying the redundancy reliability of the magnetic diagnostics layout design.This provides a design solution for the layout of the magnetic diagnostics system required to control the plasma equilibrium of CFETR,and the developed design and optimization method can provide effective support to design magnetic diagnostics systems for future magnetic confinement fusion devices.展开更多
Plasma equilibrium has been calculated using an analytical method. The plasma profiles of the current density, safety factor, pressure and magnetic surface function are obtained. The analytical solution of the Grad–S...Plasma equilibrium has been calculated using an analytical method. The plasma profiles of the current density, safety factor, pressure and magnetic surface function are obtained. The analytical solution of the Grad–Shafranov（GS） equation is obtained by the variable separation method and compared with the computed results of the equilibrium fitting code EFIT.展开更多
The EAST (HT-7U) superconducting tokamak is a national project of China on fusion research, with a capability of long-pulse (- 1000 s) operation. In order to realize a long-duration steady-state operation of EAST, som...The EAST (HT-7U) superconducting tokamak is a national project of China on fusion research, with a capability of long-pulse (- 1000 s) operation. In order to realize a long-duration steady-state operation of EAST, some significant capability of real-time control is re-quired. It would be very crucial to obtain the current profile parameters and the plasma shapes in real time by a flexible control system. As those discharge parameters cannot be directly measured, so a current profile consistent with the magnetohydrodynamic equilibrium should be evaluated from external magnetic measurements, based on a linearized iterative least square method, which can meet the requirements of the measurements. The arithmetic that the EFIT (equilibrium fitting code) is used for reference will be given in this paper and the computational efforts are reduced by parametrizing the current profile linearly in terms of a number of physical parameters. In order to introduce this reconstruction algorithm clearly, the main hardware design will be listed also.展开更多
The plasma shape and other paremeters such as /3P, li is important for the tokamak deveice where the plasma has a non-circular cross-section of sufficient elongation. The measuered signals of magnetic probes and flux ...The plasma shape and other paremeters such as /3P, li is important for the tokamak deveice where the plasma has a non-circular cross-section of sufficient elongation. The measuered signals of magnetic probes and flux loops are used to reconstruct the plasma shape and the current profile in device operation and plasma shape feed back control system. So the number and positions of magnetic probes and flux loops provides the basis of the plasma reconstruction. This paper instroduce how to use EFIT code (equilibrium fitting code) to determine the number and positions of the magnetic probes and flux loops. The simulation result is given also.展开更多
A new possible data archive format for storing huge amounts of data for EAST control anddata acquisition system is presented. This new general-purpose data archive format is network-transparent, i.e, machine-independe...A new possible data archive format for storing huge amounts of data for EAST control anddata acquisition system is presented. This new general-purpose data archive format is network-transparent, i.e, machine-independent and has been implemented in terms of XDR （eXternal Data Representation）. We test this format by using EFIT （Equilibrium Fitting） code on different operation systems, namely Linux and Windows, different processors, namely Sun and Pc, and different programs, namely in Fortran and C language. It can be easily used by different computers and different programming languages.展开更多
The equilibrium fitting code （EFIT） and its application in the J-TEXT tokamak are integrated by the Matlab language. The function of analysis and visualization to the results is added. In addition, the experiment da...The equilibrium fitting code （EFIT） and its application in the J-TEXT tokamak are integrated by the Matlab language. The function of analysis and visualization to the results is added. In addition, the experiment data measured by soft X-ray （SXR） are used to calculate plasma equilibrium as a constraint condition. The improved EFIT code is used for J-TEXT discharge and the profiles of plasma parameters such as flux function, safety factor q, pressure and current density are obtained from the reconstructed configurations.展开更多
The J-TEXT three-wave polarimeter-interferometer system(POLARIS),which measures timespace distribution of electron density and current density,has been optimized with both the optical system and the equilibrium recons...The J-TEXT three-wave polarimeter-interferometer system(POLARIS),which measures timespace distribution of electron density and current density,has been optimized with both the optical system and the equilibrium reconstruction method.The phase resolution of a Faraday rotation angle has been improved from 0.1 to 0.06 degree in chords from–0.18 to 0.18 m(plasma minor radius),and the sawtooth oscillation behavior has been detected by Faraday rotation angle measurement.By combining the POLARIS measured data and the equilibrium and fitting code(EFIT),an upgraded equilibrium reconstruction method has been developed,which provides a more accurate temporal and spatial distribution of current density and electron density.By means of the optimized POLARIS and improved equilibrium reconstruction,variations of profiles with increasing density have been carried out,under both Ohmic and electron cyclotron resonance heating discharges.展开更多
文摘The EFIT program is integrated with the high resolution laser polarimeter interferometer system（POLARIS）, the soft X-ray imaging diagnostic system（SXR） and the electron cyclotron emission radiometer（ECE） in the J-TEXT tokamak. Then some internal information about Faraday angle and the position of safety factor q=1 can be obtained as a constraint to EFIT. The modified EFIT code is used to calculate the internal parameters such as flux function, safety factor q, pressure and current density.
基金supported by National Natural Science Foundation of China(No.10835009)the National Magnetic Confinement Fusion Research Program of China(No.2012GB105000)the National Science Foundation for Young Scientists of China(No.11205191)
文摘This paper introduces the design and implementation of an interactive tool, the EASTViewer, for the visualization of plasma equilibrium reconstruction results for EAST （the Experimental Advanced Superconducting Tokamak）. Aimed at the operating system indepen- dently, Python, when combined with the PyGTK toolkit, is used as the programming language. Using modular design, the EASTViewer provides a unified interface with great flexibility. It is easy to access numerous data sources either from local data files or an MDSplus tree, and with the pre-defined configuration files, it can be extended to other tokamaks. The EASTViewer has been used as the major tool to visualize equilibrium data since the second EAST campaign in 2008, and it has been verified that the EASTViewer features a user-friendly interface, and has easy access to numerous data sources and cross-platforms.
基金Project supported by the National MCF Energy Research and Development Program of China (Grant Nos.2022YFE03010002,2018YFE0302100,and 2018YFE0301105)the National Natural Science Foundation of China (Grant Nos.11875291,11805236,11905256,and 12075285)。
文摘Plasma equilibrium reconstruction provides essential information for tokamak operation and physical analysis.An extensive and reliable set of magnetic diagnostics is required to obtain accurate plasma equilibrium.This study designs and optimizes the magnetic diagnostics layout for the reconstruction of the equilibrium of the plasma according to the scientific objectives,engineering design parameters,and limitations of the Chinese Fusion Engineering Test Reactor(CFETR).Based on the CFETR discharge simulation,magnetic measurement data are employed to reconstruct consistent plasma equilibrium parameters,and magnetic diagnostics'number and position are optimized by truncated Singular value decomposition,verifying the redundancy reliability of the magnetic diagnostics layout design.This provides a design solution for the layout of the magnetic diagnostics system required to control the plasma equilibrium of CFETR,and the developed design and optimization method can provide effective support to design magnetic diagnostics systems for future magnetic confinement fusion devices.
文摘Plasma equilibrium has been calculated using an analytical method. The plasma profiles of the current density, safety factor, pressure and magnetic surface function are obtained. The analytical solution of the Grad–Shafranov（GS） equation is obtained by the variable separation method and compared with the computed results of the equilibrium fitting code EFIT.
基金The project supported by the research on non-circular plasma controlthe Innovation Project of Magnetic Confinement Fusion Plasma Physics from Chinese Academy of Sciences(No.C03071025)
文摘The EAST (HT-7U) superconducting tokamak is a national project of China on fusion research, with a capability of long-pulse (- 1000 s) operation. In order to realize a long-duration steady-state operation of EAST, some significant capability of real-time control is re-quired. It would be very crucial to obtain the current profile parameters and the plasma shapes in real time by a flexible control system. As those discharge parameters cannot be directly measured, so a current profile consistent with the magnetohydrodynamic equilibrium should be evaluated from external magnetic measurements, based on a linearized iterative least square method, which can meet the requirements of the measurements. The arithmetic that the EFIT (equilibrium fitting code) is used for reference will be given in this paper and the computational efforts are reduced by parametrizing the current profile linearly in terms of a number of physical parameters. In order to introduce this reconstruction algorithm clearly, the main hardware design will be listed also.
基金The project supported by the National Meg-Science Engineering Project of the Chinese Government
文摘The plasma shape and other paremeters such as /3P, li is important for the tokamak deveice where the plasma has a non-circular cross-section of sufficient elongation. The measuered signals of magnetic probes and flux loops are used to reconstruct the plasma shape and the current profile in device operation and plasma shape feed back control system. So the number and positions of magnetic probes and flux loops provides the basis of the plasma reconstruction. This paper instroduce how to use EFIT code (equilibrium fitting code) to determine the number and positions of the magnetic probes and flux loops. The simulation result is given also.
基金supported by National Natural Science Foundation of China (No.10475079)
文摘A new possible data archive format for storing huge amounts of data for EAST control anddata acquisition system is presented. This new general-purpose data archive format is network-transparent, i.e, machine-independent and has been implemented in terms of XDR （eXternal Data Representation）. We test this format by using EFIT （Equilibrium Fitting） code on different operation systems, namely Linux and Windows, different processors, namely Sun and Pc, and different programs, namely in Fortran and C language. It can be easily used by different computers and different programming languages.
文摘The equilibrium fitting code （EFIT） and its application in the J-TEXT tokamak are integrated by the Matlab language. The function of analysis and visualization to the results is added. In addition, the experiment data measured by soft X-ray （SXR） are used to calculate plasma equilibrium as a constraint condition. The improved EFIT code is used for J-TEXT discharge and the profiles of plasma parameters such as flux function, safety factor q, pressure and current density are obtained from the reconstructed configurations.
基金the National MCF Energy R&D Program of China(No.2018YFE0310300)National Natural Science Foundation of China(Nos.11905080 and 51821005)。
文摘The J-TEXT three-wave polarimeter-interferometer system(POLARIS),which measures timespace distribution of electron density and current density,has been optimized with both the optical system and the equilibrium reconstruction method.The phase resolution of a Faraday rotation angle has been improved from 0.1 to 0.06 degree in chords from–0.18 to 0.18 m(plasma minor radius),and the sawtooth oscillation behavior has been detected by Faraday rotation angle measurement.By combining the POLARIS measured data and the equilibrium and fitting code(EFIT),an upgraded equilibrium reconstruction method has been developed,which provides a more accurate temporal and spatial distribution of current density and electron density.By means of the optimized POLARIS and improved equilibrium reconstruction,variations of profiles with increasing density have been carried out,under both Ohmic and electron cyclotron resonance heating discharges.
