期刊文献+

Using Poloidal Flux as Feedback Control Signal for Injected Power of LHCD in Long Pulse Discharge on HT-7 Tokamak

Using Poloidal Flux as Feedback Control Signal for Injected Power of LHCD in Long Pulse Discharge on HT-7 Tokamak
下载PDF
导出
摘要 Long pulse discharge is one of the important goals of HT-7 superconducting tokamak experiments. For ITER (International Thermonuclear Experimental Reactor) or a tokamak reactor, carrying out a steady operation is one of the main techniques. For long pulse discharges on HT-7 the poloidal flux is used as the feedback signal to control the injected power of LHCD (Low Hybrid Current Drive) system. Experimental results are presented. Long pulse discharge is one of the important goals of HT-7 superconducting tokamak experiments. For ITER (International Thermonuclear Experimental Reactor) or a tokamak reactor, carrying out a steady operation is one of the main techniques. For long pulse discharges on HT-7 the poloidal flux is used as the feedback signal to control the injected power of LHCD (Low Hybrid Current Drive) system. Experimental results are presented.
作者 沈飙 徐捍东
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2006年第4期385-389,共5页 等离子体科学和技术(英文版)
关键词 poloidal flux HT-7 tokamak long pulse discharge feedback control poloidal flux, HT-7 tokamak, long pulse discharge, feedback control
  • 相关文献

参考文献6

  • 1Equipe Tore Supra (prepared by F. Saint-Laurent).Nucl. Fusion, 2000, 40(6): 1047 - 1055
  • 2Wesson John. Tokamaks. Oxford: Clarendon Press,1997, 105 - 131
  • 3Hutchinson I H. Principles of Plasma Diagnostics.Cambridge: Cambridge University Press, 1987. 10-33
  • 4Kuang Guangli, Liu Yuexiu, Shan Jiafang, et al. Nucl.Fusion, 1999, 39(11Y): 1769 - 1774
  • 5Kessel Charles E, Jardin Stephen C, Bulmer Richard H, et al. Fusion Technology, 1996, 30:184
  • 6Wijnands T, MARTIN G. Nucl. Fusion, 1996, 36:1201- 1204

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部