[en] The programming procedure and characteristics of the software for a multichannel neutral particle energy spectrometer are described. Preliminary results obtained with the software are also presented

[en] A concise method to calculate the inductance of the TF (toroidal field) coils in the HL-2M tokamak is presented. To simplify the calculation, the TF coils are simulated using the polygon current filaments and the multiple integral is replaced by the inductance summation of two small beeline segments. The inductance of the TF coils has been calculated by using the plasma discharge data of the HL-2A tokamak, and the results show that the method is valid. (authors)

[en] HL-2A Discharge Control System consists of one or more VXI work stations so as to compose an all digital control system. The DCS are used to measure and control the poloidal coils, the main tasks of the poloidal coils are exploding, keeping and controlling the current of plasma. These coils explode plasma and keep it in the determined position

[en] The design principle and basic structure of the central control system for HL-2A Tokamak are introduced. Having been limited by manpower and money, the central control system should not be too expensive and too advanced. On the other hand, because of the complexity of the machine and the difficulty the author will encounter when operating the machine, the central control system should be advanced enough. If use the same technology for HL-1M to control HL-2A, the author would fail to fulfill authors' experiment goal. The central control system consists of software and hardware. The software mainly includes: (a) system monitor and control software; (b) discharge monitor and control software; (c) network and communication software. Hardware includes: (a) PLC for machine control, personnel protection and machine protection; and (b) VME computer, for the feedback control of the discharge

[en] A code named SE which is based on MATLAB language for editing and designing plasma shape is introduced, with its design principle, main function, operation interface and operation steps. The correctness of SE is proved effectively with traditional code SWEQU. Furthermore, these two codes are used to design and confirm the discharge parameters of two plasma shapes with medium elongation and triangularity. In order to achieve shapes with higher elongation and triangularity, the limit of circular cross section must be broken by using upper divertor coils. Finally, a plasma shape with higher elongation and triangularity is designed and its discharge parameters are provided with SE code. The design results demonstrate that with upper divertor coils energized, new plasma shapes with higher elongation and triangularity can obtained on HL-2A tokamak. These new plasma shapes lay solid foundation for improving the plasma quality on HL-2A tokamak. (authors)

[en] This is the modified version of The Preliminary Design on the Hardware and Nets of HL-2A Tokamak. In this version, centralized control as well as the field bus communication on HL-2A Tokamak is used. The hardware components and the operational theory are introduced. The questions of practice program, extensibility, centralized control, cooperation with other subsystems and the continuous adaptation of present device are all discussed. The budget of the system is detailed. To keep the step with the overall engineering constructions of HL-2A, suggestions of the time program are presented for the system design, instrument purchases, installation, construction, user program development and the final operation processes for the machine control system of HL-2A Tokamak

[en] Control problem of vertical instability of HL-2M tokamak was studied with DⅢ-D TokSys. The vertical displacement event (VDE) was controlled by the vessel and active conductors, the study of the eigenmodes and current distribution of the vessel greatly reduced the difficulty of modeling, and a mathematical model was set up and parameters of active conductors and the power supply were verified. The growth rates and maximum controllable vertical displacement for different plasma shape configurations with different elongation were calculated. Simulations for snow flake, single null and double null divertors were made in simulink environment by TokSys with a PD controller. Results show that VDE can be controlled very well for different plasma shape configurations. (authors)

No abstract available

[en] The HL-2M is a new medium-sized tokamak device being built by the Southwest Institute of Physics. It can operation the standard divertor configuration and the advanced divertor configurations such as Snowflake divertor and Tripod divertor. Because of the Poloidal Field coil close to the plasma and the flexibility of the coil power supply, the HL-2M can study the divertor physics and shape controllability with different divertor configurations. These studies provide support on configuration design, shape control and divertor physics for ITER and CFERT. This article will detail the standard divertor con: figuration, the snowflake divertor con: figuration and the tripod divertor configuration will be introduce detailed; Combined with the geometry design of the divertor target plate, the characteristics of the advanced divertor configuration at different X-point are introduced; By optimizing the Poloidal Field coil current, analyzing the controllable characteristics of the configuration, and exploring the plasma current running space under different configurations, the HL-2M has the ability to operate flexible and multi-position. At the same time, combined with the existing conditions of HL-2M, a simple and easy-to-control initial plasma configuration and its null field configuration were designed. The initial plasma breakdown conditions were designed and analyzed to support the initial discharge study of HL-2M. (authors)

[en] The measuring accuracy of magnetic probes is greatly improved by eliminating the disturbance of TF coils through a new discharge scenario, together with a careful calibration process. The measuring accuracy of flux loop is also improved by removing the clamping diodes in integrator which cause the loss of fast information. With accurate magnetic field and flux information input, the iteration and fitting process of EFIT converges quickly and outputs reliable results, which are consistent with diagnostic results achieved by Langmuir probes, H_α array and CCD image. A new self-developed plasma equilibrium reconstruction code, called sFIT, is also introduced, which outputs the plasma shape information that agrees very well with that of EFIT. (authors)