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EAST steady-state long pulse H-mode with core-edge integration for CFETR

  • X. Z. Gong
  • , A. M. Garofalo
  • , J. Huang
  • , J. P. Qian
  • , A. Ekedah
  • , R. Maingi
  • , C. T. Holcomb
  • , F. K. Liu
  • , Y. P. Zhao
  • , B. J. Xiao
  • , J. S. Hu
  • , C. D. Hu
  • , L. Q. Hu
  • , M. Wang
  • , H. D. Xu
  • , E. Li
  • , L. Zeng
  • , Q. Zang
  • , H. Q. Liu
  • , B. Lyu
  • Q. P. Yuan, K. D. Li, B. Zhang, J. Y. Zhang, T. Q. Jia, M. Q. Wu, J. L. Chen, X. Zhu, M. H. Li, X. J. Zhang, L. Zhang, Y. M. Duan, L. Wang, R. Ding, Y. W. Sun, G. S. Xu, Y. F. Liang, N. Xiang, B. N. Wan, J. G. Li
  • CAS - Institute of Plasma Physics
  • General Atomics
  • Commissariat à l’énergie atomique et aux énergies alternatives
  • Princeton Plasma Physics Laboratory
  • Chem./Materials Science Directorate

科研成果: 期刊稿件文章同行评审

23 引用 (Scopus)

摘要

A recent EAST experiment has successfully demonstrated long pulse steady-state high plasma performance scenario and core-edge integration since the last IAEA in 2018. A discharge with a duration over 60 s with β P ∼2.0, β N ∼1.6, H98y2 ∼1.3 and an internal transport barrier on the electron temperature channel is obtained with multi-RF power heating and current drive. A higher β N (β N ∼1.8, β p ∼2.0, H98y2 ∼1.3, n e/n GW ∼0.75) with a duration of 20 s is achieved by using the modulated neutral beam and multi-RF power, where several normalized parameters are close or even higher than the phase III 1 GW scenario of CFETR steady-state. High-Z impurity accumulation in the plasma core is well controlled in a low level by using the on-axis ECH. Modeling shows that the strong diffusion of TEM turbulence in the central region prevents tungsten impurity from accumulating. More recently, EAST has demonstrated compatible core-edge integration discharges in the high β p scenario: high confinement H98y2 > 1.2 with high β P ∼2.5/β N ∼2.0 and f bs ∼50% is sustained with reduced divertor heat flux at high density n e/n GW ∼0.7 and moderate q 95 ∼6.7. By combining active impurity seeding through radiative divertor feedback control and strike point splitting induced by resonant perturbation coil, the peak heat flux is reduced by 20-30% on the ITER-like tungsten divertor, here a mixture of 50% neon and 50% D2 is applied.

源语言英语
文章编号076009
期刊Nuclear Fusion
62
7
DOI
出版状态已出版 - 7月 2022

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