2004年发表的HL-2A实验论文题录

HL-2A实验研究

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2004年发表的HL-2A实验论文题录

编辑：发布时间： 2004年12月31日

序号	文章题名	作者	发表刊物	原文语言	检索
1	Recent experimental results from the HL-1M tokamak and progress in the HL-2A project	Y. Liu , et al.	Nucl. Fusion, Vol.44, No.2	英文	文摘
2	First divertor operation on the HL-2A Tokamak	YANG Qing-Wei, et al.	Chin. Phys. Lett. Vol.21, No.12	英文	文摘
3	Imaging System and Plasma Imaging on HL-2A Tokamak	Zheng Yinjia,et al.	Plasma Science & Technology, Vol.6, No.4	英文	文摘
4	Impurity Measured by VUV Spectrometer and OMA on HL-2A Tokamak	Cui Zhengying, et al.	Plasma Science & Technology, Vol.6, No.4	英文	文摘
5	Preliminary investigation of impurity and radiation behaviors in the HL-2A Tokamak	W.Li,et al.	31 st EPS Conference on Plasma Phys.,London, 28 June -2 July, 2004	英文	文摘
6	HL-2A plasma imaging	Y.J.Zheng , et al.	31 st EPS Conference on Plasma Phys.,London, 28 June -2 July, 2004	英文	文摘
7	Feedback control for plasma position on HL-2A Tokamak	Li Bo,et al.	23 rd Symposium on Fusion Technology, 20-24 September, 2004, Venice, Italy	英文	文摘
8	Numerical Simulation and Experimental Identification of Divertor Configuration in the HL-2A Tokamak	Yan Longwen, et al.	31st EPS Conference on Plasma Phys. London, 28 June - 2 July 2004	英文	文摘
9	HL-2A 装置气体击穿延迟时间	秦运文等	《核聚变与等离子体物理》 Vol.24,No.4	中文	文摘
10	HL-2A 装置等离子体可见光成像系统	郑银甲等	《核聚变与等离子体物理》 Vol.24,No.4	中文	文摘
11	HL-2A 装置偏滤器室中性气体压强的初步研究	王明旭等	《核聚变与等离子体物理》 Vol.24,No.4	中文	文摘
12	HL-2A 装置等离子体水平位移控制	李波等	《核聚变与等离子体物理》 Vol.24,No.4	中文	文摘
13	用丝电流方法快速识别 HL-2A 等离子体边界	李强等	《核聚变与等离子体物理》 Vol.24,No.3	中文	文摘
14	HL-2A 装置上一种测量等离子体位移的新方法	杨青巍等	《核聚变与等离子体物理》 Vol.24,No.2	中文	文摘
15	HL-2A 先进二维硬 X 射线成像 CCD 系统设计	杨进蔚等	《核聚变与等离子体物理》 Vol.24,No.2	中文	文摘
16	HL-2A 控制系统及其放电管理	宋显明等	《核聚变与等离子体物理》 Vol.24,No.1	中文	文摘

Preliminary investigation of impurity and radiation behaviors in the?HL-2A tokamak

W. Li, Z.Y.Cui, Y.D.Pan, J.L.Luo, J.F.Dong, Q.W.Yang, L.W.Yan, Y.Liu

Southwestern Institute of Physics, Chengdu, China

Abstract HL-2A tokamak (major radius R=165cm, minor radius a=38~45cm) has been successfully operated in limiter and single-null divertor configuration under good feedback control of plasma current and position in 2003 campaign. Parameters achieved under ohmic discharges with stainless steel wall and graphite limiter were as follows: toroidal field Bt=1.4T, plasma current Ip=168kA, plasma electron density ne=1.7¡ä1019/m3, plasma duration time t=920ms. In last campaign, glowing discharge cleaning (GDC) is used as a conventional wall conditioning technology and titanium gettering is used occasionally in closed divertor chamber during SN configuration discharges phase.As the startup phase of HL-2A operation and the first divertor tokamak device in China, it is important to identify the species of impurity, estimate the concentration of impurities and compare the different behaviors of radiation in limiter and divertor configuration. In the following, the present status of relevant diagnostics will be described and preliminary results will be presented.

HL-2A Plasma Imaging

Y.J. Zheng, Z. Feng, C.W. Luo, L. Liu, Q.W. Yang, Y. Liu

Southwestern institute of physics, Chengdu, P.R.China

Abstract HL-2A device, the first non-circular cross-section tokamak with diverter in P.R.China, has been constructed and put?into operation in 2002 and realized diverter configuration discharge. The main components were transferred from ASDEX device, IPP, Germany. Apart from boundary transport and SOL study, the HL-2A major subject is to investigate the improvement of confinement with high parameters, and lots of front physics and relevant engineering techniques by means of its special closed diverter in China (1). Plasma imaging (so called as .visible TV .or .TTV (tangential TV) .) (3) (4) is extremely useful to overview the edge and diverter structure; the plasma boundary may be identified in?principle?(2) (5). In order to satisfy?the demands of?the engineering adjustment and near real-time monitor of the device operation, plasma-imaging diagnostic has been developed.