Electrical insulation properties in a cold plasma of alumina coating for the in-vessel stabilizing shell of the RFX-mod2 fusion device

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-08-27 DOI:10.1016/j.fusengdes.2024.114638
Luigi Cordaro , Matteo Zuin , Luca Peruzzo , Domenico Abate , Roberto Cavazzana , Bruno Laterza , Luca Lotto , Simone Peruzzo
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Abstract

This paper presents the results of experimental tests on samples made of copper coated with alumina layer, performed to assess the reliability of its dielectric properties for applications in the low temperature plasma at the edge of a fusion device. The cue of the study was related to the plasma facing components of the RFX-mod2 fusion device (Marrelli et al., 2019, Peruzzo et al., 2023, Peruzzo et al., 2019), devoted to the experimental study of the magnetic confinement of fusion plasmas in a variety of configurations, including the reversed-field pinch and the tokamak. In RFX-mod2 an in-vacuum copper shell for the passive stabilization of MHD modes will surround the plasma. To avoid potentially harmful electrical discharges, which could be induced by rapid transients of the plasma current, this structure must be covered with an electrically insulating layer. For RFX-mod2 an alumina coating was chosen, whose dielectric properties have been tested both in air and in the presence of weakly ionized plasma. Electrical tests, conducted on copper samples with alumina deposits of about 100μm thickness, revealed that the ceramic layer has a high electrical resistance value in air (>1GΩ), but electrical discharges can occur in presence of a weakly ionized plasma, depending on compactness and porosity of the alumina layer, causing local melting of the alumina and expulsion of copper droplets from the substrate. Scanning Electron Microscope (SEM) analyses revealed that in the failed samples the ceramic layer was irregular and rough, with interconnected cavities and cracks, which could reduce its effective thickness and explain the dielectric breakdown at relatively low voltages (<400V). The analyses also showed that samples with a more compact layer present a higher dielectric strength in the presence of the plasma, highlighting that compactness and porosity play crucial roles in ensuring good insulation for materials in a plasma. This study led the definition of the requirements for the insulating coating of the plasma facing components of the RFX-mod2 fusion machine, however the results can be useful for other fusion and non-fusion plasma applications requiring electrical insulation, which can span from industrial devices to spacecrafts.

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用于 RFX-mod2 聚变装置腔内稳定壳体的氧化铝涂层在冷等离子体中的电绝缘性能
本文介绍了对涂有氧化铝层的铜制样品进行实验测试的结果,目的是评估其在核聚变装置边缘低温等离子体中应用的介电性能的可靠性。这项研究的线索与 RFX-mod2 核聚变装置(Marrelli 等人,2019 年;Peruzzo 等人,2023 年;Peruzzo 等人,2019 年)中面向等离子体的组件有关,该装置致力于对各种配置(包括反向场夹持和托卡马克)中核聚变等离子体的磁约束进行实验研究。在 RFX-mod2 中,等离子体周围将环绕一个用于被动稳定 MHD 模式的真空铜壳。为了避免等离子体电流的快速瞬变可能引起的潜在有害放电,该结构必须覆盖一层电绝缘层。我们为 RFX-mod2 选择了氧化铝涂层,并在空气中和弱电离等离子体中测试了其介电性能。在厚度约为 100μm 的氧化铝沉积铜样品上进行的电气测试表明,陶瓷层在空气中具有较高的电阻值(1GΩ),但在存在弱电离等离子体的情况下会发生放电,这取决于氧化铝层的致密性和孔隙率,放电会导致氧化铝局部熔化,铜滴会从基底上排出。扫描电子显微镜(SEM)分析表明,在失效样品中,陶瓷层不规则且粗糙,存在相互连接的空洞和裂缝,这可能会减少其有效厚度,从而解释了在相对较低的电压(<400V)下发生介电击穿的原因。分析还显示,陶瓷层更紧密的样品在等离子体中具有更高的介电强度,这说明紧密度和孔隙率在确保材料在等离子体中具有良好的绝缘性能方面起着至关重要的作用。这项研究确定了 RFX-mod2 核聚变机面向等离子体部件的绝缘涂层要求,但研究结果也适用于其他需要电气绝缘的核聚变和非核聚变等离子体应用,包括工业设备和航天器。
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来源期刊
Fusion Engineering and Design
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.
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