Global gyrokinetic simulations of electrostatic microturbulent transport in LHD stellarator with boron impurity

ORAL

Abstract

Global gyrokinetic simulations of electrostatic microturbulent transport for discharge # 166256 of the LHD stellarator are carried out in the presence of boron impurity using the gyrokinetic toroidal code (GTC). The simulations show the co-existence of the ion temperature gradient (ITG) turbulence and trapped electron mode (TEM) turbulence before and during boron powder injection. ITG turbulence dominates in the core, whereas TEM dominates near the edge, consistent with the experimental observations. Linear TEM frequency increases from ∼ 80 kHz to ∼ 100 kHz during boron injection, and the ITG linear frequency decreases from ∼ 20 kHz to ∼ 13 kHz, consistent with the experiments. The poloidal wave number spectrum is broad for both ITG: 0 − 0.5 mm−1 and TEM: 0 − 0.25 mm−1 . The nonlinear simulations with boron impurity show a reduction in the turbulent transport compared to the case without boron. The comparison of the nonlinear transport shows that the ion heat transport is substantially reduced in the region where the TEM is dominant. However, the average electron heat transport throughout the radial domain and the average ion heat transport in the region where the ITG is dominant are similar. The simulations with boron show the effective heat conductivity values qualitatively agree with the estimate obtained from the experiment.

*This work is supported by the National Supercomputing Mission (Ref No: DST/NSM/R&D HPC Applications/2021/4), Board of Research in Nuclear Sciences (BRNS Sanctioned No. 57/14/04/2022-BRNS), Science and Engineering Research Board EMEQ program (SERB sanctioned no. EEQ/2022/000144). A.S. thanks the Indian National Science Academy (INSA) for their support under the INSA Senior Scientist Fellowship scheme. This work was conducted within the framework of the NIFS/PPPL International Collaboration and it is supported by the US DOE under Contract No. DE-AC02-09CH11466 with Princeton University. This work was partially supported by the US Department of Energy under Award No. DE-SC0018270 (SciDAC ISEP Center) and DE-FG02-07ER54916. This work has used the resources of the Param Pravega supercomputer at the Indian Institute of Science, Bangalore, India.

Publication: Nuclear Fusion 63, under review (2023)

Presenters

  • Tajinder Singh

    • Department of Physics, Indian Institute of Science, Bangalore 560012, India
    • Indian Institute of Science, Bangalore, India

Authors

  • Tajinder Singh

    • Department of Physics, Indian Institute of Science, Bangalore 560012, India
    • Indian Institute of Science, Bangalore, India
  • Javier H. Nicolau

    • Department of Physics and Astronomy, University of California, Irvine, California 92697, USA
  • Federico Nespoli

    • Princeton Plasma Physics Laboratory, Princeton, NJ 08540, USA
    • Princeton Plasma Physics Laboratory
  • Gen Motojima

    • National Institute for Fusion Science, National Institutes of Natural Sciences, 322-6 Oroshi-cho, Toki, Gifu 509-5292, Japan
  • Zhihong Lin

    • University of California, Irvine
    • Department of Physics and Astronomy, University of California, Irvine, California 92697, USA
  • Abhijit Sen

    • Inst for Plasm Res
    • Institute for Plasma Research, Bhat, Gandhinagar 382428, India
  • Sarveshwar Sharma

    • Institute for Plasma Research, Bhat, Gandhinagar 382428, India
  • Animesh Kuley

    • Department of Physics, Indian Institute of Science, Bangalore 560012, India
    • Indian Institute of Science Bangalore