Coupling circuit model and discharge waveform prediction for Keda Torus eXperiment

Bai, Wei; Lan, Tao; Lee, Yang; Xiao, C.; Mao, Wenzhe; You, Wei; Li, Chenguang; Tu, Cui; Tan, Manqing; Luo, Bin; Fu, Chengshuo; Huang, Fangchen; Xu, Henghui; Deng, Tijian; Zhu, Jiawei; Fu, Peng; Xu, Wen; Zhou, Haiyang; Wang, Hai; Wan, Shude; Liu, Ahdi; Xie, Jinlin; Li, Hong; Ding, W. X.; Liu, Wandong

doi:10.1016/j.fusengdes.2015.07.025

Cited by 8 publications

(4 citation statements)

References 30 publications

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“…Second, the total current of each sector of the EQ coil (1, 6), (2, 5) and (3, 4) must be the same. The circuit in figure 9 [15] shows that the three sectors of the OH coil have the same current and that the circuit is compatible with the OH field design. To fulfill the above design, the physical design ideas are as follows: the total current in each group of EQ coils is the same, and the three sectors of OH coils that are connected in parallel should have the same current and voltage.…”

Section: Optimization Of the Pf Systemmentioning

confidence: 84%

Design of the poloidal field system for KTX

You

Mao

2018

Plasma Sci. Technol.

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The design of the poloidal field (PF) system includes the ohmic heating field system and the equilibrium (EQ) field system, and is the basis for the design of a magnetic confinement fusion device. A coupling between the poloidal and plasma currents, especially the eddy current in the stabilizing shell, yields design difficulties. The effects of the eddy current in the stabilizing shell on the poloidal magnetic field also cannot be ignored. A new PF system design is thus proposed. By using a low-μ material (μ=0.001, ε=1) instead of a conductive shell, an electromagnetic model is established that can provide a continuous eddy current distribution on the conductive shell. In this model, a 3D time-domain problem with shells translates into a 2D magnetostatic problem, and the accuracy of the calculation is improved. Based on these current distributions, we design the PF system and analyze how the EQ coils and conductive shell affect the plasma EQ when the plasma ramps up. To meet the mainframe design requirements and achieve an efficient power-supply design, the position and connection of the poloidal coils are optimized further.

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Section: Optimization Of the Pf Systemmentioning

confidence: 84%

Design of the poloidal field system for KTX

You

Mao

2018

Plasma Sci. Technol.

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“…The KTX power supply system includes ohmic heating power supply (OHPS), equilibrium field power supply (EQPS), and toroidal field power supply (TFPS) [22]. In particular, the EQPS has been designed and will be manufactured in the next phase [23].…”

Section: Power Supply Systemsmentioning

confidence: 99%

Overview of Keda Torus eXperiment initial results

et al. 2017

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The Keda Torus eXperiment (KTX) is a new reversed field pinch (RFP) device at the University of Science and Technology of China. The construction and assembly of KTX, including the vacuum chamber, conducting shell, magnetic field windings, power supply system, active control coils, vacuum pump and data acquisition system, have been completed on August 1, 2015. Immediately following that, the first plasma was obtained on August 15, 2015. Intensive conditioning of the machine is underway to ramp up the plasma current toward its full operation. An active feedback mode control system has been built and has been implemented to control the error field around the vertical gaps of the conducting shell. The pulsed power supply systems of ohmic heating field and toroidal field (TF), using thyristor and energy storage capacitors, have been tested and commissioned. The TF power supply has flexibility in being able to operate with a reversed TF configuration and stable TF configuration. The fundamental diagnostic tools are developed for early KTX operation. Currently, the plasma current is up to 205 kA and the maximum discharge length is 21 ms, approaching to the conducting shell penetration time. Furthermore, typical RFP discharges are being produced with RFP state lasting 2 ms. These initial operation results for KTX are described in detail.

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“…Early reversed field pinches (RFPs) [10][11][12][13] have rarely equipped with reciprocating probe due to short discharge durations. However, a plasma profile diagnostic tool is urgently needed for Keda Torus eXperiment (KTX) [14][15][16][17][18][19][20][21][22][23][24][25][26][27][28][29] RFP. According to the experiences on tokamaks, a fast scanning probe system is designed to measure the plasma edge potential, density, and temperature profiles on the KTX RFP.…”

Section: Introductionmentioning

confidence: 99%

Fast radial scanning probe system on KTX

Deng¹,

Lan²,

Tan³

2020

Plasma Sci. Technol.

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A fast radial scanning probe system was constructed for the Keda Torus eXperiment (KTX) to measure the profiles of boundary plasma parameters such as floating potential, electron density, temperature, transport fluxes, etc. The scanning probe system is driven by slow and fast motion mechanisms, corresponding to the stand-by movement of a stepping motor and the fast scanning movement of a high-torque servo-motor, respectively. In fast scanning, the scanner drives the probe radially up to 20 cm at a maximum velocity of 4.0 m s −1 . A noncontact magnetic grating ruler with a high spatial resolution of 5 μm is used for the displacement measurement. New scanning probe can reach the center of plasmas rapidly. The comparison of plasma floating potential profiles obtained by a fixed radial rake probe and the single scanning probe suggests that the high-speed scanning probe system is reliable for measuring edge plasma parameter profiles on the KTX device.

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Coupling circuit model and discharge waveform prediction for Keda Torus eXperiment

Cited by 8 publications

References 30 publications

Design of the poloidal field system for KTX

Design of the poloidal field system for KTX

Overview of Keda Torus eXperiment initial results

Fast radial scanning probe system on KTX

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