Development of a translation stage for beam studies in the negative ion source SPIDER

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-09-05 DOI:10.1016/j.fusengdes.2025.115413

R. Agnello , M. Barbisan , L. Lotto , R. Pasqualotto , B. Zaniol , G. Serianni

引用次数: 0

Abstract

Beam diagnostics play a crucial role in characterizing the beam performances of SPIDER, the prototype negative ion source for the ITER neutral beam injection system. To enhance the alignment and spatial resolution of Beam Emission Spectroscopy (BES) diagnostics, a remotely controlled translation stage capable of sub-millimeter accuracy has been developed. This stage allows dynamic adjustments of lines-of-sight (LOS) to improve alignment with individual beamlets and enable detailed scans of the beam for homogeneity and divergence studies. Preliminary tests demonstrate the system’s ability to measure beam divergence and intensity variations with high precision, validating its potential for optimizing beam performance. Future applications include advanced studies of single beamlet divergence, validation of emission codes, and support for MITICA diagnostics.

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负离子源SPIDER中束流研究转换台的研制

作为ITER中性束流注入系统的原型负离子源SPIDER，束流诊断在表征其束流性能方面起着至关重要的作用。为了提高光束发射光谱（BES）诊断的准直性和空间分辨率，研制了一种亚毫米精度的遥控平移台。该阶段允许动态调整视线（LOS），以改善与单个光束的对齐，并能够对光束进行详细扫描，以进行均匀性和发散性研究。初步测试表明，该系统能够高精度测量光束发散和强度变化，验证了其优化光束性能的潜力。未来的应用包括单束散度的高级研究，发射代码的验证，以及对MITICA诊断的支持。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.