Comparative study of PVD techniques for tungsten deposition onto graphite substrate for fusion application

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

Fusion Engineering and Design Pub Date : 2025-04-09 DOI:10.1016/j.fusengdes.2025.115016

Alžběta Endrychová , Slavomír Entler , Vojtěch Smolík , Tomáš Polcar , Jan Walter , Jan Podaný

引用次数: 0

Abstract

Graphite tiles are used as heat shields to protect components exposed to high-temperature plasma due to their high thermal resistance, and low atomic number, which reduces the maintenance requirements and the effect of plasma contamination. However, sputtering and hydrogen affinity are the main limitations for graphite. Tungsten has high energy threshold for sputtering and resistance to chemical erosion. Application of tungsten layer on graphite substrate may overcome graphite's limitations. This study explores the HiPIMS technique for depositing tungsten coating and tungsten coating with molybdenum interlayers onto graphite substrates. The aim was to study the influence of surface roughness on the adhesion, mechanical properties, and microstructure of coatings to optimize coated graphite for plasma-facing materials.

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PVD技术在石墨基板上熔敷钨的比较研究

石墨瓦由于其高热阻和低原子序数，减少了维护要求和等离子体污染的影响，被用作隔热罩来保护暴露在高温等离子体中的部件。然而，溅射和亲氢是石墨的主要限制。钨具有较高的溅射能量阈值和抗化学腐蚀能力。在石墨基板上应用钨层可以克服石墨的局限性。本研究探索了在石墨基底上沉积钨涂层和含钼中间层钨涂层的HiPIMS技术。目的是研究表面粗糙度对涂层附着力、力学性能和微观结构的影响，以优化等离子表面材料的涂层石墨。

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.