Morphological modification of Rh-C coatings upon low-energy Ar+ ion sputtering

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Artem M. Dmitriev , Moïse Gonda , Fabien Sanchez , Laurent Marot , Roland Steiner , Pierre-Olivier Renault , Ernst Meyer
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Abstract

In ITER, the metallic first mirrors (FMs) will undergo erosion due to their proximity to the fusion plasma and deposition of materials of the first wall, leading to mirror reflectivity's decrease. In vacuo plasma cleaning is foreseen for restoration of the FMs' optical properties by means of ion sputtering. Previously, it was shown that cyclic cleaning of polished metallic mirrors can lead to the development of pits due to low carbon amounts in the bulk mirror. The pitting formation is detrimental to the mirror's optical properties. This study aims to investigate the influence of carbon concentration on mirror morphology changes due to cyclic low-temperature plasma irradiation. Five rhodium (Rh) and carbon (C) coatings with different amounts of C were deposited on a pure Rh film on top of polished stainless steel substrates. All the samples were prepared by magnetron sputtering using a single or dual magnetron. Prior to each cycle of the plasma cleaning, a 20 nm layer of Al2O3 was deposited on the Rh-C samples. The plasma discharge was created with argon gas using a 60 MHz radio frequency excitation and resulted in the complete removal of the alumina layer after each cycle. The surface morphology of the mirrors was characterized by employing scanning electron microscopy (SEM) and focused ion beam (FIB). After the cyclic cleaning, the coatings containing carbon have failed, showing either partial delamination, cracking, or total delamination. Additionally, all the mirrors demonstrated the formation of mounds on the surface, while 17 at.% of carbon in the film led to the development of pits. The mechanisms of coating failure and such morphological modification are discussed in the paper.
低能 Ar+ 离子溅射对 Rh-C 涂层的形态改性
在热核聚变实验堆中,金属第一反射镜(FMs)会因接近聚变等离子体和第一反射镜壁材料的沉积而受到侵蚀,导致反射镜反射率下降。为了恢复 FMs 的光学特性,预计将通过离子溅射进行真空等离子清洗。以前的研究表明,对抛光的金属镜面进行循环清洗会因镜面中的碳含量较低而导致凹坑的形成。凹坑的形成不利于镜面的光学特性。本研究旨在探讨碳浓度对循环低温等离子辐照导致的镜面形貌变化的影响。在抛光不锈钢基底上的纯 Rh 薄膜上沉积了五层不同含量的铑 (Rh) 和碳 (C) 涂层。所有样品都是通过使用单磁控管或双磁控管进行磁控溅射制备的。在每次等离子清洗循环之前,在 Rh-C 样品上沉积一层 20 纳米的 Al2O3。等离子体放电是用氩气在 60 MHz 射频激励下产生的,每次循环后氧化铝层都会被完全清除。利用扫描电子显微镜(SEM)和聚焦离子束(FIB)对反射镜的表面形态进行了表征。循环清洗后,含碳涂层失效,出现部分脱层、开裂或完全脱层。此外,所有镜子的表面都形成了小丘,而薄膜中 17% 的碳会导致凹坑的形成。本文讨论了涂层失效和这种形态改变的机理。
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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