COMPASS 托卡马克上的 80keV 1 MW NBI：结果和运行经验

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-14 DOI:10.1016/j.fusengdes.2025.115078

I. Mysiura , K. Bogar , O. Ficker , M. Komm , F. Jaulmes , J. Varju , S. Fukova , P. Vondracek , M. Hron , R. Panek , COMPASS Team

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引用次数: 0

摘要

在COMPASS托卡马克的最后实验活动之前，它的加热系统被升级为1兆瓦，80 keV的中性束注入（NBI）装置，补充了现有的两个40 keV， 300 kW的NBI。这次升级显著提高了托卡马克的性能，实现了2 keV的中心电子温度，等离子体存储能量增加了30%，中子产量提高了8倍，并且可以在反向环向磁场中运行h模式。实验测试证实，该系统符合其技术规格，提供1兆瓦的中性光束功率，光束发散度为12 mrad，从而验证了其适用于COMPASS-U。然而，整合过程揭示了技术和设计方面的挑战，为缓解战略和未来改进提供了宝贵的见解。COMPASS-U项目计划包括多达6个类似的注入器，这使得从这次升级中获得的操作经验对未来的托卡马克操作至关重要。此外，活动期间收集的数据突出了COMPASS辅助系统的局限性，包括水冷却性能、接地方案和其他基础设施要求。这些发现将为未来托卡马克和NBI系统的优化提供信息，并确保下一代托卡马克实验的稳健性能。

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80keV 1 MW NBI on COMPASS tokamak: the results and operational experience

Prior to the final experimental campaign of the COMPASS tokamak, its heating system was upgraded with the 1 MW, 80 keV Neutral Beam Injection (NBI) unit, complementing the existing two 40 keV, 300 kW NBIs. This upgrade significantly improved tokamak performance, achieving a central electron temperature of 2 keV, a 30 % increase in plasma stored energy, an eightfold rise in neutron yield, and enabling H-mode operation in a reversed toroidal magnetic field.

Experimental tests confirmed that the system met its technical specifications, delivering 1 MW of neutral beam power with a beam divergence of <12 mrad, thereby validating its suitability for COMPASS-U. However, the integration process revealed technical and design challenges, which provided valuable insights for mitigation strategies and future improvements. The COMPASS-U project plans to incorporate up to six similar injectors, making the operational experience gained from this upgrade critical for future tokamak operations.

Furthermore, the data collected during the campaign highlighted limitations in COMPASS's auxiliary systems, including water cooling performance, grounding schemes, and other infrastructure requirements. These findings will inform the optimization of the future tokamak and NBI's systems and ensure robust performance in next-generation tokamak experiments.

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来源期刊

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.