Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas
作者: M.A. JaworskiT. AbramsJ.P. AllainM.G. BellR.E. BellA. DialloT.K. GrayS.P. GerhardtR. KaitaH.W. KugelB.P. LeBlancR. MaingiA.G. McLeanJ. MenardR. NygrenM. OnoM. PodestaA.L. RoquemoreS.A. SabbaghF. ScottiC.H. SkinnerV.A. SoukhanovskiiD.P. Stotlerthe NSTX Team
作者单位: 1Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA
2School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907, USA
3Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
4Lawrence Livermore National Laboratory, Livermore, CA 94551, USA
5Sandia National Laboratory, Albuquerque, NM 87185, USA
6Department of Applied Physics and Applied Mathematics, Columbia University, New York, NY 10027, USA
刊名: Nuclear Fusion, 2013, Vol.53 (8)
来源数据库: Institute of Physics Journal
DOI: 10.1088/0029-5515/53/8/083032
原始语种摘要: Liquid metal plasma-facing components (PFCs) have been proposed as a means of solving several problems facing the creation of economically viable fusion power reactors. To date, few demonstrations exist of this approach in a diverted tokamak and we here provide an overview of such work on the National Spherical Torus Experiment (NSTX). The Liquid Lithium Divertor (LLD) was installed and operated for the 2010 run campaign using evaporated coatings as the filling method. The LLD consisted of a copper-backed structure with a porous molybdenum front face. Nominal Li filling levels by the end of the run campaign exceeded the porosity void fraction by 150%. Despite a nominal liquid level exceeding the capillary structure and peak current densities into the PFCs exceeding 100 kA m−2,...
全文获取路径: IOP 

  • lithium 
  • divertor 分流偏滤器
  • performance 性能
  • plasma 深绿玉髓
  • tokamak 托卡马克
  • exceeding 过度的
  • interacting 相克的
  • overview 概观
  • facing 车端面
  • material 充填料