Nuclear Fusion (Jan 2024)

ECW assisted plasma startup with low toroidal electric field and full metal wall in EAST superconducting tokamak

  • Wenbin Liu,
  • Jinping Qian,
  • Hongjuan Sun,
  • Hyun-Tae Kim,
  • Runze Chen,
  • Bin Zhang,
  • Handong Xu,
  • Zhengping Luo,
  • Yaowei Yu,
  • Wei Gao,
  • Ang Ti,
  • Hailin Zhao,
  • Haiqing Liu,
  • Shouxin Wang,
  • Ling Zhang,
  • Guizhong Zuo,
  • Pan Li,
  • Kedong Li,
  • Tianqi Jia,
  • Zuhao Wang,
  • Wei Wang,
  • Zhongfang Gaun,
  • Yutong Guo,
  • Xianzu Gong,
  • the EAST Team

DOI
https://doi.org/10.1088/1741-4326/ad8c62
Journal volume & issue
Vol. 64, no. 12
p. 126072

Abstract

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Recent experimental results from the EAST superconducting tokamak with a full metal wall (without Li-coating) provide strong support for the ITER startup scheme with electron cyclotron wave (ECW) assistance. Detailed investigations were performed on the impact of different magnetic field geometries, including quadrupolar field configuration (QFC), wide null field configuration (NFC), and trapped particle configuration (TPC). All three configurations enabled the breakdown of neutral gas with ECW pre-ionization. However, in most discharges with QFC, the absence of closed flux surfaces after the breakdown was associated with unsuccessful plasma startups. Conversely, both NFC and TPC achieved successful plasma startups under normal conditions, with TPC demonstrating higher robustness against high impurity levels compared to NFC. Experiments found that the minimum ECW power required for a successful TPC startup is approximately 0.48 MW. Plasma startup failed if the prefill gas pressure exceeded optimal levels for a given ECW power ( $ \unicode{x2A7E} {\text{0}}{\text{.48}}$ MW), with the critical gas pressure linearly dependent on the ECW power. Additionally, higher ECW power was required with increased impurity levels. With ECW assistance, the toroidal electric field at $R = 1.85{\text{ m}}$ in EAST routine operations ( ${{ < }}0.15{\text{ V}}\,{{\text{m}}^{ - 1}}$ ) is significantly lower than ITER’s maximum value (0.3 V m ^−1 ), suggesting the possibility of reducing flux consumption and lowering demands on coils and power supplies for ITER.

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