| Poloidal Field Control for the HT—7U Superconducting Tokamak |
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| 引用本文： | 罗家融,王华忠,赵皖平.Poloidal Field Control for the HT—7U Superconducting Tokamak[J].等离子体科学和技术,2002,4(5):1445-1455. |
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| 作者姓名： | 罗家融 王华忠 赵皖平 |
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| 作者单位： | InstituteofPlasmaPhysics,ChineseAcademyofSciences,Hefei230031,China |
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| 基金项目： | This work was supported by the National Meg-science Engineering Project of the Chinese Government |
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| 摘 要： | Controlling the poloidal field(PF) in the HT-7U superconducting tokamak is critical to the realization of the mission of advanced tokamak research.Plasma start-up,plasma position,shape,current control and plasma shape reconstruction have been performed as a part of its design process.The PF coils have been designed to produce a wide range of plasmas,Plasma start-up can be achieved for multiple conditions.Fast controlling coils for plasma position inside the vacuum vessel are sued for controloling the plasma vertical position on a short timescale.The PF coils control the plasma current and shape on a slower timescale,VXI(VME bus extensions for Instrumentation)Bus system and DSP(Digital Signal Processor is a basic unit of the feedback control system),the response time of which is about(2-4)ms.The basic unit of this system ,the shape-controlling algorithms of a few critical points on plasma boundary and real-time equilibrium fitting(RTEFIT)will be described in this paper.
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| 关 键 词： | 超导体托卡马克 等离子体控制 数字信号处理器 |
Poloidal Field Control for the HT-7U Super conducting Tokamak |
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| LUO Jia-rong WANG Hua-zhong ZHAO Wan-pingInstitute of Plasma Physics,Chinese Academy of Sciences,Hefei ,China.Poloidal Field Control for the HT-7U Super conducting Tokamak[J].Plasma Science & Technology,2002,4(5):1445-1455. |
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| Authors: | LUO Jia-rong WANG Hua-zhong ZHAO Wan-pingInstitute of Plasma Physics Chinese Academy of Sciences Hefei China |
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| Affiliation: | LUO Jia-rong WANG Hua-zhong ZHAO Wan-pingInstitute of Plasma Physics,Chinese Academy of Sciences,Hefei 230031,China |
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| Abstract: | Controlling the poloidal field (PF) in the HT-7U superconducting tokamak is critical to the realization of the mission of advanced tokamak research. Plasma start-up, plasma position, shape, current control and plasma shape reconstruction have been performed as a part of its design process. The PF coils have been designed to produce a wide range of plasmas. Plasma start-up can be achieved for multiple conditions. Fast controlling coils for plasma position inside the vacuum vessel are used for controlling the plasma vertical position on a short timescale. The PF coils control the plasma current and shape on a slower timescale. VXI (VME bus extensions for Instrumentation) Bus system and DSP (Digital Signal Processor is a basic unit of the feedback control system), the response time of which is about (2-4) ms. The basic unit of this system, the shape-controlling algorithms of a few critical points on plasma boundary and real-time equilibrium fitting (RTEFIT) will be described in this paper. |
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| Keywords: | plasma control VXI Bus equilibrium start-up DSP |
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