期刊文献+

Plasma Shape and Current Control Simulation of HT-7U Tokamak 被引量:1

Plasma Shape and Current Control Simulation of HT-7U Tokamak
下载PDF
导出
摘要 This paper describes the discharge simulation of HT-7U tokamak plasma equilibrium and plasma current by solving MHD equations and surface average transport equations using an equilibrium evolution code. The simulated result shows the evolution of plasma parameter versus time.The simulated result can play an important role in the design of the plasma equilibrium and control system of a tokamak. This paper describes the discharge simulation of HT-7U tokamak plasma equilibrium and plasma current by solving MHD equations and surface average transport equations using an equilibrium evolution code. The simulated result shows the evolution of plasma parameter versus time.The simulated result can play an important role in the design of the plasma equilibrium and control system of a tokamak.
作者 吴斌 张澄
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2003年第1期1625-1631,共7页 等离子体科学和技术(英文版)
基金 The project supported by the National Nature Science Foundation of China (No. 10135020)
关键词 discharge simulation control system numerical simulation discharge simulation, control system, numerical simulation
  • 相关文献

参考文献3

  • 1YU Q Q. HT-7U tokamak physics design. Institute of Plasma Physics, Academia Sinica, 1999
  • 2Jardin S C, Pomphrey N, Hoffmann F. Dynamic modeling of transport and positional control of tokamaks. Journal of Computational Physics,1986, 66:481
  • 3Hoffmann F, Jardin S C, et al. Application of a new algorithm to plasma shape control in BPX.Nuclear Fusion, 1992, 32:897

同被引文献10

  • 1吴宜灿,柯严,郑善良,汪卫华,储德林,黄群英,刘晓平,许德政,王红艳,黄德所,朱晓翔,高纯静,李静惊,陈义学,吴斌,汪太平,柏云清,章毛连,刘松林,罗月童,刘萍,李春京,李强,童莉莉,翁晓毅,吴磊,王祥科,FDS课题组.聚变驱动次临界堆概念设计研究[J].核科学与工程,2004,24(1):72-80. 被引量:53
  • 2[2]Wu Y C, Qian J P, Yu J N. The fusion-driven hybrid system and its material selection[J]. Journal of nuclear materials, 2002,307~311 :1629~1636.
  • 3[3]Wu Yican. Progress in fusion-driven hybrid system studies in China[J]. Fusion Engineering and Design,2002,63~64:73~80.
  • 4[4]Wu Bin. Introduction of fusion driven subcritical system plasma design [J]. Fusion Engineering and Design,2003,66~68 : 181~ 186.
  • 5[5]Jardin S C, Batke C G. , et al. Physics basis for a tokamak fusion power plant[J]. Fusion Engineering and design, 2000,48:281~298.
  • 6[6]Hively L M. Convenient computational Forms for Maxwellian Reactivitics[J]. Nuclear fusion, 1977,17: 873~876.
  • 7[7]Aymarl R, et al. The ITER design[J]. Plasma Phys. Control. Fusion, 2002,44:519~565.
  • 8[8]Description of Jsolver Vl. 3 input file INEQU, PPPL,1999.
  • 9[9]Jardin S C,Kessel C E,G. Bathke C, et al. Physics basis for a reversed shear tokamak power plant[J]. Fusion Engineering and Design, 1997,38:27~57.
  • 10储德林,吴斌,吴宜灿,邓小玖.Preliminary Analysis of Advanced Equilibrium Configuration for the Fusion-Driven Subcritical System[J].Plasma Science and Technology,2003,5(6):2085-2092. 被引量:4

引证文献1

二级引证文献10

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