KSTAR 新安装的下钨分流器启动实验

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jeongwon Lee, Jayhyun Kim, Hyunsun Han, Youngho Lee, Sang-hee Hahn, Jun-Gyo Bak, Mi Joung, Hyungho Lee, Yong-Un Nam
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引用次数: 0

摘要

在 KSTAR 2023 等离子体活动期间,对 KSTAR 将下部分流器从碳升级为钨之后的等离子体启动实验进行了研究。舱内涡流,特别是在环形方向上分流器支撑结构上诱发的涡流,由于下分流器配置的升级而发生了显著变化。这些变化可能会影响等离子体启动阶段的极性场配置,而极性场配置对于氘中性气体的可靠击穿和烧穿以及等离子体电流的稳定上升至关重要。在此,我们介绍了考虑到这些升级的新启动方案的开发过程。我们利用真空磁场设计代码来估算由于新的分流器配置而导致的极磁场变化。对启动方案进行了修改,以补偿涡流的不同影响,并在 KSTAR 2023 活动的初始阶段进行了实验验证和优化。本文介绍了启动方案的最终版本和等离子体启动数据,并在 KSTAR 活动的剩余时间内确认了新启动方案的可靠性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Startup experiment with the newly installed lower tungsten divertor of KSTAR
Plasma startup experiments after the KSTAR upgrade of a lower divertor from carbon to tungsten have been studied during the KSTAR 2023 plasma campaign. In-vessel eddy currents, especially those induced on the divertor supporting structure in the toroidal direction, are significantly altered by the upgrade of the lower divertor configuration. These changes could affect the poloidal field configuration of the plasma startup phase, which is essential for the reliable breakdown and burn-through of deuterium neutral gas and the stable rise of the plasma current. Here, we present the development process of a new startup scenario that considers these upgrades. The vacuum magnetic field design code was utilized to estimate the changes in the poloidal field due to the new divertor configuration. Modifications to the startup scenario were prepared to compensate for the different effects of eddy currents, and experimental validation and optimization were performed during the initial phase of the KSTAR 2023 campaign. The final version of the startup scenario and plasma startup data are presented, and the reliability of the new startup scenario was also confirmed throughout the remainder of the KSTAR campaign.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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