Corrosion behavior and mechanical properties of SiC/SiC composite joints with Y2O3-Al2O3-SiO2 interlayer under high-temperature steam environments at 1200 °C

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-03-30 DOI:10.1016/j.jnucmat.2025.155798

Shaobo Yang , Chenxi Liang , Jiali Li , Yujie Ma , Sijie Kou , Juanli Deng , Bo Chen , Shangwu Fan

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Abstract

The study investigated the corrosion behavior and mechanical performance of SiC/SiC composite joints with Y₂O₃-Al₂O₃-SiO₂ (YAS) interlayers under high-temperature steam environments at 1200 °C. Under low-flow conditions, partial disruption of Si-O and Al-O bonds in the YAS glass network reduced crosslinking, forming an aluminosilicate protective layer that inhibited further corrosion. Prolonged exposure led to Y³⁺ migration and accumulation, resulting in Y₂Si₂O₇ precipitation and growth. High-flow conditions caused a thinner glass layer, continuous longitudinal cracks, and more severe erosion and dissolution of the YAS glass due to higher steam velocity. Despite these degradations, the joints exhibited satisfactory performance, maintaining shear strengths of about 40 ± 2 MPa after 15 h of low-flow exposure and about 36 ± 5 MPa after 5 h of high-flow exposure. These findings demonstrate that YAS interlayers provide excellent corrosion resistance and mechanical stability as a sealant for nuclear-grade SiC/SiC.

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含Y2O3-Al2O3-SiO2中间层SiC/SiC复合材料接头在1200℃高温蒸汽环境下的腐蚀行为和力学性能

研究了Y2O3-Al2O3-SiO2 （YAS）夹层SiC/SiC复合材料接头在1200℃高温蒸汽环境下的腐蚀行为和力学性能。在低流量条件下，YAS玻璃网络中Si-O和Al-O键的部分断裂减少了交联，形成了铝硅酸盐保护层，抑制了进一步的腐蚀。长时间暴露导致Y3+迁移积累，导致Y2Si2O7析出生长。高流量条件下，由于蒸汽流速的增大，使得YAS玻璃的玻璃层变薄，纵向裂纹不断，侵蚀和溶解更加严重。尽管存在这些退化，但节理表现出令人满意的性能，在低流量暴露15小时后保持约40±2 MPa的抗剪强度，在高流量暴露5小时后保持约36±5 MPa的抗剪强度。这些发现表明，作为核级SiC/SiC的密封胶，YAS夹层具有优异的耐腐蚀性和机械稳定性。

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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.