Liquid lithium loop system to solve challenging technology issues for fusion power plant
作者: M. OnoR. MajeskiM.A. JaworskiY. HirookaR. KaitaT.K. GrayR. MaingiC.H. SkinnerM. ChristensonD.N. Ruzic
作者单位: 1Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543, United States of America
2National Institute for Fusion Science, 322-6 Oroshi, Toki, Gifu 509-5292, Japan
3Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831, United States of America
4University of Illinois, Urbana-Champaign, IL 61801, United States of America
刊名: Nuclear Fusion, 2017, Vol.57 (11)
来源数据库: Institute of Physics Journal
DOI: 10.1088/1741-4326/aa7f41
原始语种摘要: Steady-state fusion power plant designs present major divertor technology challenges, including high divertor heat flux both in steady-state and during transients. In addition to these concerns, there are the unresolved technology issues of long term dust accumulation and associated tritium inventory and safety issues. It has been suggested that radiation-based liquid lithium (LL) divertor concepts with a modest lithium-loop could provide a possible solution for these outstanding fusion reactor technology issues, while potentially improving reactor plasma performance. The application of lithium (Li) in NSTX resulted in improved H-mode confinement, H-mode power threshold reduction, and reduction in the divertor peak heat flux while maintaining essentially Li-free core plasma operation even...
全文获取路径: IOP 

  • lithium 
  • fusion 融解
  • plant 植物
  • recovery 回收
  • reactor 反应器
  • divertor 分流偏滤器
  • tritium 
  • reduction 减少
  • removal 消去
  • level 水准