摘要
EHL-2 is a compact, high-field spherical tokamak designed to explore the potential of an advanced p-11B nuclear fusion reactor. Due to its high plasma current and thermal energy, it is crucial to mitigate the impact associated with disruptions to ensure the safe operation of EHL-2. This paper evaluates the performance requirements of the disruption prediction system on EHL-2, with a particular focus on applying generalizable knowledge transfer from existing devices to future ones. Furthermore, the key characteristics of disruption mitigation strategies are analyzed, and their overall mitigation performance on EHL-2 is assessed. This insight provides valuable guidance for optimizing the engineering design of EHL-2 and identifying its optimal operational regime.
| 源语言 | 英语 |
|---|---|
| 期刊论文编号 | 024013 |
| 期刊 | Plasma Science and Technology |
| 卷 | 27 |
| 期 | 2 |
| DOI | |
| 出版状态 | 已出版 - 1 2月 2025 |
学术指纹
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