Taming the plasma–material interface with the 'snowflake' divertor in NSTX
作者: V.A. SoukhanovskiiJ.-W. AhnR.E. BellD.A. GatesS. GerhardtR. KaitaE. KolemenB.P. LeBlancR. MaingiM. MakowskiR. MaquedaA.G. McLeanJ.E. MenardD. MuellerS.F. PaulR. RamanA.L. RoquemoreD.D. RyutovS.A. SabbaghH.A. Scott
刊名: Nuclear Fusion, 2011, Vol.51 (1), pp.012001 (4pp)
来源数据库: Institute of Physics Journal
DOI: 10.1088/0029-5515/51/1/012001
英文摘要: Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high-power density divertors. A novel 'snowflake' divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry benefits for divertor heat flux mitigation, such as an increased plasma-wetted area and a higher divertor volume available for volumetric power and momentum loss processes, as compared with the standard divertor. Both a significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with core H-mode confinement in discharges with the SFD using only a minimal set of poloidal field coils.
全文获取路径: IOP 

  • snowflake 雪花
  • divertor 分流偏滤器
  • interface 界面
  • plasma 深绿玉髓
  • material 充填料