Abstract
This paper reports on the extension of our amplitude-based resonant magnetic perturbation (RMP) edge localized mode (ELM) controller to support phasing control (relative toroidal phases of RMP waveforms between rows of coils), multiple toroidal mode numbers, and new ‘jump’ and ‘probing’ strategies, all deployed on KSTAR and DIII-D. By treating the control algorithm as device-independent and adjusting only the real-time interfaces to sensors and power supplies, we have confirmed that the same finite state machine—based feedback logic can be ported between machines with minor modifications. In experiments using n = 2 RMPs on KSTAR and n = 3 on DIII-D, the controller successfully modulated RMP amplitudes in real time to sustain ELM suppression while minimizing confinement degradation. Phasing control broadened the suppression window, as it permitted the system to avoid locked-mode regions and safely access ELM-free conditions. A rotating RMP phasing scheme, integrated into the same framework, distributes divertor heat loads more uniformly, making it a promising strategy for protecting plasma-facing components during long discharges. New ‘jump’ and ‘probing’ techniques demonstrate the possibility for the controller to preempt imminent ELMs and refine the minimum required RMP amplitude without returning to ELMy conditions. Taken together, these upgrades enable extended ELM-free operation while mitigating confinement degradation, providing a practical framework for real-time ELM control in future high-performance tokamaks.
| Original language | English |
|---|---|
| Article number | 086021 |
| Journal | Nuclear Fusion |
| Volume | 65 |
| Issue number | 8 |
| DOIs | |
| State | Published - Aug 1 2025 |
Funding
The authors would like to thank the KSTAR and DIII-D teams. Additionally, we would like to thank CheolSik Byun and Minseok Kim for their valuable contributions to this work. This material is based upon work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Award(s) DE-FC02-04ER54698. In addition this material was supported by the U.S. Department of Energy, under Awards DE-SC0020372, DE-AC05-00OR22725, DE-SC0022270, DE-SC0021968, DE-AC02-09CH11466, DE-SC0015480 and DE-AC52-07NA27344. This research was also supported by R&D Program of ‘High Performance Tokamak Plasma Research & Development (EN2501-16)’ and ‘Korea-US Collaboration Research for High Performance Plasma on Tungsten Divertor (EN2503-01)’ through the Korea Institute of Fusion Energy (KFE) funded by the Government funds, Republic of Korea.
Keywords
- DIII-D
- ELM suppression
- KSTAR
- RMP
- adaptive feedback control
- feedback
- fusion plasma
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