Impurity transport studies in NSTX neutral beam heated H-mode plasmas
作者: L. Delgado-AparicioD. StutmanK. TritzM. FinkenthalS. KayeR. BellR. KaitaB. LeBlancF. LevintonJ. MenardS. PaulD. SmithH. Yuh
刊名: Nuclear Fusion, 2009, Vol.49 (8), pp.085028 (10pp)
来源数据库: Institute of Physics Journal
DOI: 10.1088/0029-5515/49/8/085028
原始语种摘要: The first experimental assessment of low-Z impurity transport in a neutral beam heated, high-confinement H-mode plasma sustained in a low-field, low-aspect ratio spherical tokamak, was performed at the National Spherical Torus Experiment (NSTX). The injected impurities penetrate to the core on a hundred millisecond time scale, indicating a low core particle diffusivity ( 1 m2 s−1) in good agreement with the values predicted by neoclassical transport theory. In addition, a fixed q -profile magnetic field scan that showed reduced impurity penetration at high fields is also reported. This result suggests that anomalous ion particle transport associated with turbulent long-wavelength electrostatic instabilities must be largely suppressed in the NSTX core.
全文获取路径: IOP 

  • neutral 中性的
  • transport 输运
  • heated 加热的