降低高温蒸汽环境下铬涂层 Zr 合金的氧化率：外层 Zr 涂层的方法

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

Journal of Nuclear Materials Pub Date : 2024-09-20 DOI:10.1016/j.jnucmat.2024.155421

Yanguang Cui , Man Zhang , Jianqiao Yang , Junkai Liu , Xintao Zhang , Qifeng Zeng , Junqiang Lu , Fen Zhao , Dayan Ma , Di Yun

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引用次数: 0

摘要

人们普遍认为铬涂层锆合金是很有前途的事故耐受燃料（ATF）包层材料。然而，由于铬涂层在氧化和扩散过程中消耗很快，因此需要很厚的涂层，这不利于中子经济性。本研究在铬涂层的顶部制作了一层薄的锆涂层作为保护层，旨在降低铬涂层的氧化消耗率。为确定氧化动力学，进行了原位增重测量。分析了涂层/基体界面和氧化物/涂层界面的微观结构演变。结果表明，Zr-Cr 涂层 Zr 合金样品的增重率低于裸 Cr 涂层 Zr 合金样品。在涂层中观察到由 Cr/Zr 混合氧化物组成的等轴晶粒结构，这有助于抑制元素扩散并降低 Cr 涂层的氧化率。在 1000 ℃ 蒸汽氧化 4 小时后，样品结构由 Zr 基体、Cr2Zr 层、残余 Cr 涂层、Cr2O3 层、Cr/Zr 混合氧化物层和 ZrO2 层组成。

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Reducing the oxidation rate of Cr-coated Zr alloys under high temperature steam environment: An approach of an outer Zr coating

Cr-coated Zr alloys are widely regarded as promising accident-tolerant fuel (ATF) cladding materials. However, the rapid consumption of the Cr coating through both oxidation and diffusion demands a thick coating, which is detrimental to neutron economic. In this study, a thin Zr coating was fabricated on the top of the Cr coating to act as a protective layer, aiming to reduce the oxidation consumption rate of Cr coatings. In-situ weight gain measurements were performed to determine the oxidation kinetics. The microstructural evolution of the coating/substrate interface and the oxide/coating interface were analyzed. The results show that the weight gain rate of the Zr-Cr coated Zr alloy sample is lower than that of the bare Cr-coated Zr alloy samples. An equiaxed grain structure composed of Cr/Zr mixed oxides was observed in the coating, which helps to inhibit elements diffusion and reduce the oxidation rate of Cr coatings. After steam oxidation at 1000 °C for 4 h, the sample structure consisted of the Zr substrate, a Cr₂Zr layer, a residual Cr coating, a Cr₂O₃ layer, a Cr/Zr mixed oxides layer, and a ZrO₂ layer.

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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.