Mechanical and microstructural characterization of thermally grown alumina on Kanthal APMT

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Peter Beck , Md. Mehadi Hassan , Arjen van Veelen , Tarik Saleh , Christopher Matthews , Erofili Kardoulaki , Benjamin Eftink
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引用次数: 0

Abstract

Thermally grown α-alumina layers on Kanthal APMT were characterized and mechanically tested. Different growth durations and post growth heat treatments were evaluated. Gaugeless ring pull tests were conducted with digital image correlation to measure the spallation strain of the oxide layer, providing tens of separate measurements per test. The strain at oxide spallation failure had significant spread with average failure occurring at 0.5 - 2 % strain in both tension and compression. It was also found that the failure strain was dependent on oxide thickness with the thicker 2 and 3 µm oxides tending to fail at lower strains. The thicker oxide layers also experienced more catastrophic failure, with larger spallation flakes leaving more of the base metal exposed. Transmission Kikuchi diffraction was used to characterize the microstructure of the oxide layer. All oxide layers showed columnar grains with grain boundaries extending across the entire thickness of the oxide.
Kanthal APMT上热生长氧化铝的力学和微观结构表征
对Kanthal APMT上热生长的α-氧化铝层进行了表征和力学测试。对不同的生长时间和生长后热处理进行了评价。采用数字图像相关技术进行无规格环拉试验,以测量氧化层的剥落应变,每次试验提供数十个单独的测量。氧化层剥落破坏时的应变有明显的扩展,平均破坏发生在拉伸和压缩应变的0.5 ~ 2%。破坏应变与氧化物厚度有关,较厚的2µm和3µm氧化物在较低应变下容易破坏。较厚的氧化层也经历了更多灾难性的失败,更大的剥落薄片使更多的贱金属暴露在外。透射菊池衍射表征了氧化层的微观结构。所有氧化层均呈柱状晶粒,晶界延伸至氧化层的整个厚度。
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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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