Development of SiC encapsulation for thulium oxide targets as potential nuclear batteries

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-04-01 Epub Date: 2025-02-17 DOI:10.1016/j.jnucmat.2025.155700

Brandon Shaver , Kip Wheeler , Caen Ang

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Abstract

The design, fabrication and properties of encapsulations for radioisotope fuel targets (¹⁶⁹Tm) were assessed. Elemental analysis and phase identification by X-ray Fluorescence and X-ray Diffraction showed a SiC encapsulation of a thulium oxide ceramic. Microhardness testing of the encapsulation showed a relatively consistent hardness of 32.2 ± 4.7 GPa across the vertices and walls, with a mid-plane join hardness of 30.1 ± 5.4 GPa. Manufacturing tolerances followed a normal distribution with a standard deviation (σ) of σ _OD = ± 0.014 mm and σ_ID = ± 0.037 mm for Tm₂O₃ and SiC. The design of the target emphasizes robust, radiation-tolerant, high-strength SiC, but heat transfer is likely axially asymmetric because contact between Tm₂O₃-SiC is limited. Tm₂O₃-SiC chemical compatibility testing was investigated, indicating a possible reaction-limited process below 1873 K, and a possible diffusion-limited process above 1873 K. At higher temperatures, thulium containment for this concept is limited by chemical compatibility.

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潜在核电池用氧化铥靶材SiC封装研究进展

对放射性同位素燃料靶材（169Tm）封装材料的设计、制造和性能进行了评价。x -射线荧光和x -射线衍射的元素分析和物相鉴定表明，氧化铥陶瓷包被碳化硅。包封体显微硬度测试显示，包封体顶点和管壁的硬度相对一致，为32.2±4.7 GPa，包封体中间连接硬度为30.1±5.4 GPa。Tm2O3和SiC的加工公差服从正态分布，标准差σ OD =±0.014 mm, σ id =±0.037 mm。靶材的设计强调坚固、耐辐射、高强度的SiC，但由于Tm2O3-SiC之间的接触有限，传热可能是轴向不对称的。研究了Tm2O3-SiC的化学相容性，表明在1873 K以下可能存在反应限制过程，在1873 K以上可能存在扩散限制过程。在较高的温度下，这种概念的铥容器受到化学相容性的限制。

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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.