期刊文献+

HT—7U超导托卡马克真空室设计 被引量:5

下载PDF
导出
摘要 介绍HT-7U超导托卡马克真空室的材料选择、结构特点、受力分析、烘烤与冷却以及真空室内部相关部件的概况。
出处 《真空科学与技术》 CSCD 北大核心 1999年第A10期32-36,共5页 Vacuum Science and Technology
  • 相关文献

同被引文献24

  • 1Wan Y X. Overview progress project [C]. 21st IAEA FEC, 16-21 October 2006. and future plan of EAST OV/1-1, Chengdu, China,.
  • 2Xiang Gao et al.[J]. Nucl. Fusion 47 (2007) 1353.
  • 3Hu J S et al.Deposits removal and hydrogen release on exposure co-deposited films to O-ICR and O-GDC plasmas in HT-7 [J].Plasma Phys. Control. Fusion, 2007,49:421-434.
  • 4Hu J S et al.RF wall conditioning in EAST [C].9th ITPA-SOL/Divetor, May 7-10, 2007,Graching, Germany.
  • 5Yang Yet al.Vacuum operation of first divertor campaign Experimental Advanced Superconducting Tokamak (EAST) [C]. 17th International Vacuum Congress, Stockholm July 2-6, 2007.
  • 6达道安.真空设计手册[M].北京:国防工业出版社,1999.558-581.
  • 7Wu Songtao,Weng Peide.The project of HT-7U and its progress[A].Proceedings of Fifteenth International Conference on Magnet Technology(MT-15)[C].1998.
  • 8Shen B,Wang B N,Zhang X Q.Diamagnetic measurement on HT-7 Superconducting Tokamak[J].Fusion engineering and design,2004,70:311.
  • 9Besshou T,Tomiyama K,Kpndo K.Diamagnetic doubleloop method for a highly sensitive measurement of energy stored In a stellarator plasma[J].Rev.Sci.Instrum.,2001,72(10):3859.
  • 10T. Tanabe. Tritium fuel cycle Issues in handling lm'ge amount Nuclear Materials,2013,438 :SI 9 in ITER and DEMO: of fuel [J]. Journal of - $26.

引证文献5

二级引证文献19

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