Design of the upgraded Glow Discharge Cleaning system for RFX-mod2

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

Fusion Engineering and Design Pub Date : 2025-06-11 DOI:10.1016/j.fusengdes.2025.115228

M. Fadone , R. Cavazzana , S. Ciufo , L. Grando , S. Peruzzo , A. Rizzolo , M. Zuin

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Abstract

RFX-mod2 represents the upgraded version of the RFX-mod experiment, a toroidal fusion machine proficient in operating in both Reversed Field Pinch and Tokamak configurations. Located at the Consorzio RFX facility in Padova, Italy, this experiment features a major radius of 2 meters and a minor radius of 0.5 meters. The initial part of experimental campaigns for these machines is always a cleaning procedure of the first wall of the camber by means of the Glow Discharge Cleaning (GDC). GDC for RFX-mod2 will be sustained thanks to the revamped former GDC system that consists of 2 movable electrodes. Moreover, 8 new fixed electrodes will be installed as Plasma Facing Components (PFC) to guarantee a more uniform plasma expansion, and therefore cleaning, of the first wall. This paper describes the design of the new fixed electrodes for the RFX-mod2 GDC system and experimental tests for the plasma ignition with fixed and movable electrodes in order to validate the overall RFX-mod2 GDC revamped system.

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RFX-mod2升级版辉光放电清洗系统设计

RFX-mod2是RFX-mod实验的升级版，它是一台精通反向场捏缩和托卡马克配置的环形聚变机。该实验位于意大利帕多瓦的Consorzio RFX设施，其主要半径为2米，次要半径为0.5米。这些机器的实验活动的初始部分通常是通过辉光放电清洗（GDC）对弧面的第一面墙进行清洗。RFX-mod2的GDC系统由2个可移动电极组成，经过改造后的GDC系统将保持不变。此外，将安装8个新的固定电极作为等离子体面向组件（PFC），以保证更均匀的等离子体膨胀，从而清洁第一壁。本文介绍了RFX-mod2 GDC系统新型固定电极的设计，以及固定电极和活动电极的等离子点火实验测试，以验证RFX-mod2 GDC改造系统的整体有效性。

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.