Divertor heat flux mitigation in high-performance H-mode discharges in the National Spherical Torus Experiment
作者: V.A. SoukhanovskiiR. MaingiD.A. GatesJ.E. MenardS.F. PaulR. RamanA.L. RoquemoreR.E. BellC.E. BushR. KaitaH.W. KugelB.P. LeBlancD. Muellerthe NSTX Team
刊名: Nuclear Fusion, 2009, Vol.49 (9), pp.095025 (10pp)
来源数据库: Institute of Physics Journal
DOI: 10.1088/0029-5515/49/9/095025
英文摘要: Experiments conducted in high-performance 1.0 and 1.2 MA 6 MW NBI-heated H-mode discharges with a high magnetic flux expansion radiative divertor in NSTX demonstrate that significant divertor peak heat flux reduction and access to detachment may be facilitated naturally in a highly shaped spherical torus (ST) configuration. Improved plasma performance with high βt = 15–25%, a high bootstrap current fraction f BS = 45–50%, longer plasma pulses and an H-mode regime with smaller ELMs has been achieved in the strongly shaped lower single null configuration with elongation κ = 2.2–2.4 and triangularity δ = 0.7–0.8. Divertor peak heat fluxes were reduced from 6–12 to 0.5–2 MW m−2 in ELMy H-mode discharges using the inherently high magnetic flux expansion f...
全文获取路径: IOP 

  • National 国民牌大客车
  • mitigation 水的软化
  • performance 性能