Contact angle measurements of liquid lithium on surface-modified stainless steel, insulating materials, and other metals and coatings

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

Fusion Engineering and Design Pub Date : 2024-09-05 DOI:10.1016/j.fusengdes.2024.114649

Steven Stemmley , Braden Moore , Cody Moynihan , Oren Yang , Kristin Skrecky , David Ruzic

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引用次数: 0

Abstract

Liquid lithium plasma facing components (PFCs) may provide an attractive alternative to more conventional solid PFCs due to improved plasma performance and the reduction of erosion and wall damage issues. Conceptual designs for liquid lithium divertors have been proposed, but a complete understanding of the interaction between liquid lithium and structural materials will be required for their successful implementation. One aspect of the interaction is the wetting of different materials by liquid lithium at temperatures relevant to fusion applications.

Contact angle measurements were used to study the wetting of liquid lithium on 304 stainless steel with varying surface roughnesses, metallic coatings, advanced alloys, and insulating materials in the temperature range from 200 °C to 350 °C. A mirror finish on 304 stainless steel was found to decrease the contact angle and lower the critical wetting temperature while all rougher 304 stainless steel treatments behaved similarly. For thin film coatings and other alloys, the surface roughness was found to impact the wettability more than the change in chemical composition. Compatibility issues with all three insulating materials tested are discussed and limited contact angle data was collected for these samples.

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液态锂在表面改性不锈钢、绝缘材料及其他金属和涂层上的接触角测量结果

液态锂等离子体面组件（PFCs）可改善等离子体性能，减少侵蚀和壁面损坏问题，从而为更传统的固态 PFCs 提供有吸引力的替代品。目前已经提出了液态锂分流器的概念设计，但要成功实施这些设计，还需要全面了解液态锂与结构材料之间的相互作用。接触角测量用于研究在 200 °C 至 350 °C 的温度范围内，液态锂对具有不同表面粗糙度的 304 不锈钢、金属涂层、高级合金和绝缘材料的润湿情况。研究发现，304 不锈钢表面的镜面处理会减小接触角并降低临界润湿温度，而所有较粗糙的 304 不锈钢处理则表现类似。对于薄膜涂层和其他合金，表面粗糙度对润湿性的影响大于化学成分的变化。讨论了与所有三种测试绝缘材料的兼容性问题，并为这些样品收集了有限的接触角数据。

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.