Air oxidation kinetics of erbium trihydride and hydrogen permeation mechanism in Er2O3 layer

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-14 DOI:10.1016/j.jnucmat.2025.155702

Mingwang Ma, Xing Wang, Zhoushilin Ruan, Han Wang, Lei Wang, Binghua Tang, Xiaohua Tan

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Abstract

The hydrogen permeation barrier is crucial in minimizing the loss of hydrogen isotopes from structural components, particularly in applications such as hydrogen storage systems and fusion reactors. In this study, Er₂O₃ layers were synthesized on erbium trihydride (ErH₃) powder surfaces through air oxidation. Oxidation kinetics were examined within the temperature range of 100 to 300 °C, and the kinetic parameters were identified, leading to the suggestion of grain boundary diffusion controlling mechanism. Focused ion beam scanning electron microscope (FIB-SEM), X-ray photoelectron spectroscopy (XPS) and X-ray diffraction (XRD) were employed to analyze the cross-sectional microstructure, crystal structure and chemical composition of the pre-oxidized samples. Thermal desorption spectroscopy (TDS) observations suggested that the low-temperature peak was affected by hydrogen diffusion through the Er₂O₃ layer, whereas the high-temperature desorption peak associated with β-ErH₂ decomposition was unaffected due to the dissolution and reduction of oxide layer. A hydrogen permeation model was introduced to calculate the activation energy for hydrogen permeation through the Er₂O₃ layer formed on ErH₃.

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三氢化铒在Er2O3层中的空气氧化动力学及氢渗透机理

氢渗透屏障对于最大限度地减少结构部件中氢同位素的损失至关重要，特别是在氢储存系统和聚变反应堆等应用中。本研究采用空气氧化法在三氢化铒（ErH3）粉末表面合成了Er2O3层。在100 ~ 300℃范围内进行了氧化动力学研究，确定了动力学参数，提出了晶界扩散控制机制。利用聚焦离子束扫描电镜（FIB-SEM）、x射线光电子能谱（XPS）和x射线衍射仪（XRD）分析了预氧化样品的截面微观结构、晶体结构和化学成分。热解吸光谱（TDS）结果表明，低温解吸峰受Er2O3层中氢扩散的影响，而与β-ErH2分解相关的高温解吸峰不受氧化层溶解和还原的影响。引入氢渗透模型，计算氢通过ErH3上形成的Er2O3层的活化能。

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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.