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

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

Journal of Nuclear Materials Pub Date : 2025-02-17 DOI:10.1016/j.jnucmat.2025.155700

Brandon Shaver , Kip Wheeler , Caen Ang

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引用次数: 0

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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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.