Effects of irradiation on interfacial strength and microstructure of double-layer mullite and alumina coating on SiC

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-09-15 DOI:10.1016/j.jnucmat.2024.155410

Taichi Miyagishi , Sosuke Kondo , Hirokazu Katsui , Kiyohiro Yabuuchi , Ryutaro Usukawa , Yasuyuki Ogino , Hao Yu , Ryuta Kasada

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Abstract

Silicon carbide (SiC) ceramics hold great potential for use in nuclear-reactor components due to characteristics such as high-temperature strength and low activation. Despite their resistance against corrosion in harsh environments, they suffer elevated corrosion rates under particle irradiation. Thin anti-corrosion coatings, such as mullite bond layers and alumina top layers, are essential to enhance the irradiation stability of SiC. The objective of this study was to evaluate the irradiation stability of a double-layer coating developed to enhance the corrosion resistance of SiC in nuclear applications. The coating, which comprised a mullite bond layer and an alumina top layer, was applied to a SiC substrate using laser chemical vapor deposition. Irradiation experiments were conducted at 300 °C with 5.1-MeV Si ions up to 10 displacements per atom. To assess the interfacial strength, a novel testing method, called the double-notch shear compression testing method, was developed based on ASTM standards and was implemented using a nanoindenter. This approach enabled precise measurements of the mechanical integrity at the interfaces of the coating under irradiation. The results showed an increase in the interfacial strength at the SiC/mullite and alumina/mullite interfaces with irradiation. Microstructural analysis of the fracture surface through scanning electron microscopy–energy-dispersive X-ray spectroscopy revealed that cracks propagated within the mullite layer, indicating the presence of mullite on the fracture surface. Transmission electron microscopy (TEM) images indicated that a 2-µm-thick transition layer existed at the SiC/mullite interface but not at the alumina/mullite interface. The TEM–electron energy loss spectroscopy suggested that the Al-O bonding structures in the transition layer were changed from tetrahedral (AlO₄) to octahedral (AlO₆) through irradiation, and this structural transition may directly affect the strength.

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辐照对碳化硅双层莫来石和氧化铝涂层界面强度和微观结构的影响

碳化硅（SiC）陶瓷具有高温强度和低活化等特性，因此在核反应堆部件中具有巨大的应用潜力。尽管碳化硅陶瓷在恶劣环境中具有抗腐蚀性，但在粒子辐照条件下，其腐蚀率会升高。薄防腐蚀涂层（如莫来石结合层和氧化铝面层）对于提高碳化硅的辐照稳定性至关重要。本研究的目的是评估一种双层涂层的辐照稳定性，该涂层是为提高碳化硅在核应用中的耐腐蚀性而开发的。该涂层由莫来石结合层和氧化铝表层组成，采用激光化学气相沉积方法涂覆在碳化硅基底上。辐照实验是在 300 °C 温度下用 5.1-MeV Si 离子进行的，每个原子的位移高达 10 次。为了评估界面强度，根据 ASTM 标准开发了一种名为 "双缺口剪切压缩测试法 "的新型测试方法，并使用纳米压头进行了实施。这种方法可以精确测量辐照下涂层界面的机械完整性。结果表明，随着辐照的进行，SiC/莫来石和氧化铝/莫来石界面的界面强度有所增加。通过扫描电子显微镜-能量色散 X 射线光谱法对断裂表面进行的微观结构分析表明，裂纹在莫来石层内传播，表明断裂表面存在莫来石。透射电子显微镜（TEM）图像显示，在碳化硅/莫来石界面上存在 2 微米厚的过渡层，而在氧化铝/莫来石界面上则没有。透射电子显微镜-电子能量损失光谱表明，通过辐照，过渡层中的 Al-O 键合结构从四面体（AlO4）变为八面体（AlO6），这种结构转变可能直接影响强度。

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来源期刊

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.