Radio frequency wall conditioning discharges in argon atmosphere at Uragan-2 M stellarator

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

Fusion Engineering and Design Pub Date : 2025-04-29 DOI:10.1016/j.fusengdes.2025.115131

Yu.V. Kovtun , A.V. Lozin , V.E. Moiseenko , M.M. Kozulya , A.N. Shapoval , R.O. Pavlichenko , V.N. Bondarenko , D.I. Baron , S.M. Maznichenko , V.B. Korovin , E.D. Kramskoy , A.Yu. Krasiuk , V.S. Romanov , Yu.P. Martseniuk , I.E. Garkusha , S. Brezinsek , A. Dinklage , the Uragan-2 M Team

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Abstract

Two scenarios of radio frequency wall conditioning (RFWC) in the argon atmosphere at low magnetic field were investigated at Uragan-2 M stellarator. In the first scenario, a stellarator magnetic field is used to confine plasma of a RFWC discharge. In the second scenario RFWC discharge was realised in pure toroidal magnetic field. The plasma parameters were measured for different values of neutral gas pressure and RF power. In the RFWC discharge, the average plasma density up to ∼ 1 × 10¹⁸ m⁻³ was observed. Plasma ion composition and charges states were identified using the optical emission spectroscopy. The partial pressures of residual gases in the vacuum chamber were measured with a mass-spectrometer during series of the wall conditioning discharges. Measurements showed a decrease in water partial pressure of ∼ 50–51 % after the wall conditioning procedure for both scenarios.

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在uragan - 2m仿星器的氩气中射频壁调节放电

在uragan - 2m仿星器上研究了低磁场氩气环境下射频壁调节（RFWC）的两种情况。在第一种情况下，仿星器磁场被用来限制RFWC放电的等离子体。在第二种情况下，在纯环形磁场中实现RFWC放电。在不同的中性气体压力和射频功率下测量了等离子体参数。在RFWC放电中，平均等离子体密度高达~ 1 × 1018 m−3。利用发射光谱法确定了等离子体离子的组成和电荷态。用质谱仪测量了真空室壁面调节放电过程中残余气体的分压。测量结果显示，在两种情况下，经过壁面调节程序后，水分压降低了约50 - 51%。

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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.