Preliminary results on the removal of retained hydrogen by ECR discharge cleaning in Helimak

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

Fusion Engineering and Design Pub Date : 2025-08-20 DOI:10.1016/j.fusengdes.2025.115397

Shuqi Yang , Yaowei Yu , Xiang Zhu , Muquan Wu , Hang Li , Gongshun Li , Fei Wen , Xiaodong Lin , Xiang Gao

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引用次数: 0

Abstract

The Helimak is a compact toroidal steady-state device that has been reassembled and upgraded at Shenzhen University to serve as a dedicated platform for wall-conditioning studies. In this work, electron cyclotron resonance (ECR) plasma cleaning driven by 2.45 GHz radio frequency (RF) waves is systematically investigated. The effects of the toroidal magnetic field (TF), RF power, and wall temperature on hydrogen removal are quantified. Lowering TF from 0.098 T to 0.048 T shifts the ECR resonance layer closer to the inner wall, significantly enhancing cleaning efficiency. Increasing RF power from 3 to 8 kW raises the plasma density and further improves removal performance. Elevating the wall temperature to 90°C provides an additional boost; at 8 kW, the removal rate at 90°C is approximately 5.5 times higher than that at room temperature. These findings highlight the importance of resonance positioning and elevated wall temperature for effective hydrogen decontamination, and they support the feasibility of Electron Cyclotron Wall Conditioning (ECWC) techniques in future fusion devices.

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赫利马克ECR放电清洗法去除残留氢的初步结果

Helimak是一种紧凑的环形稳态装置，在深圳大学重新组装和升级，作为壁面调节研究的专用平台。本文系统地研究了2.45 GHz射频波驱动下的电子回旋共振等离子体清洗。量化了环向磁场、射频功率和壁温对脱氢的影响。将TF从0.098 T降低到0.048 T，使ECR共振层更靠近内壁，显著提高了清洗效率。将射频功率从3千瓦增加到8千瓦，提高了等离子体密度，进一步提高了去除性能。将壁温提高到90°C可以提供额外的增压；当功率为8kw时，在90°C下的去除率大约是室温下的5.5倍。这些发现强调了共振定位和提高壁温对有效除氢的重要性，并支持了电子回旋壁调节（ECWC）技术在未来聚变装置中的可行性。

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.