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

• Published in: Nuclear fusion 2024-12, Vol.64 (12), p.126072
• Main Authors: Liu, Wenbin, Qian, Jinping, Sun, Hongjuan, Kim, Hyun-Tae, Chen, Runze, Zhang, Bin, Xu, Handong, Luo, Zhengping, Yu, Yaowei, Gao, Wei, Ti, Ang, Zhao, Hailin, Liu, Haiqing, Wang, Shouxin, Zhang, Ling, Zuo, Guizhong, Li, Pan, Li, Kedong, Jia, Tianqi, Wang, Zuhao, Wang, Wei, Gaun, Zhongfang, Guo, Yutong, Gong, Xianzu
• Format: Article
• Language: English
• Subjects: EAST; ECW; full metal wall; plasma startup
• ISSN: 0029-5515; 1741-4326
• DOI: 10.1088/1741-4326/ad8c62

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 ( ⩾ 0 .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 m in EAST routine operations ( < 0.15 V 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.