发表机构
Columbia University; Columbia Fusion Research Center; General Atomics; Princeton Plasma Physics Laboratory; Korea Institute of Fusion Energy（哥伦比亚大学; 哥伦比亚聚变研究中心; 通用原子能公司; 普林斯顿等离子体物理实验室; 韩国聚变能源研究所）
机构由 AI 辅助整理，请以论文原文为准。AI 中文总结
本文在KSTAR单次H模放电中通过岛愈合实现非破坏性误差场识别，将罗盘扫描放电次数从四次减至一次，节省75%时间，为未来托卡马克部署奠定基础。
AI 中文摘要
在KSTAR装置上，通过岛愈合方法在单次H模放电中实现了非破坏性罗盘扫描误差场识别。该方法可将完成完整罗盘扫描所需的操作时间减少高达75%，将所需放电次数从四次减少到一次。此前在DIII-D、JET和MAST-U上的实验已在欧姆和L模下展示了该技术，但需要多次放电，并且需要靠近等离子体的强实时n=1磁诊断，这对于未来装置可能不可行。本文结果是通过在KSTAR等离子体控制系统中实施一组与聚变试点电厂运行相关的新触发算法，并结合KSTAR强大的共振磁扰动（RMP）和长脉冲持续时间而实现的。这代表了无破坏性误差场识别方法向未来抗破坏性托卡马克（包括ITER和聚变试点电厂）部署迈出的重要一步。文中还讨论了弥补剩余差距以实现可行性的必要步骤。
英文摘要
Non-disruptive compass scan error field identification via island healing is demonstrated on KSTAR in a single H-mode discharge. This method can allow for up to a 75% reduction in the operational time necessary for a complete compass scan by reducing the required discharges from four to one. Previous experiments on DIII-D, JET, and MAST-U have demonstrated the technique in Ohmic and L-mode but required multiple discharges and strong real-time n=1 magnetics diagnostics close to the plasma that are unlikely to be viable for future devices. The results presented here were made possible by implementing a new set of triggering algorithms relevant to fusion pilot plant operation into the KSTAR plasma control system, along with KSTAR's strong RMPs and long pulse lengths. This represents a significant step towards the disruption-free error field identification method being demonstrated for deployment on future disruption-averse tokamaks, including ITER and fusion pilot plants. Steps needed to close remaining gaps to viability are addressed.
