Uranium nitride from uranyl citrate gel combustion and electrospray-assisted granulation

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

Journal of Nuclear Materials Pub Date : 2025-07-15 DOI:10.1016/j.jnucmat.2025.156036

Walter Bonani, Jacobus Boshoven, Marco Cologna

引用次数: 0

Abstract

We report a novel synthesis route for uranium nitride via carbothermal reduction and nitridation of a precursor obtained by combusting a uranyl citrate gel under argon. The gel combustion results in a powder in which nanometric UO₂ islands are finely dispersed in a carbon matrix. This powder was then granulated via a novel electrospray-assisted granulation method and finally carbothermally reduced under a nitrogen atmosphere to yield single-phase UN. The UN granules were then densified to high density via spark plasma sintering, while conventional pressure-less sintering resulted in low density.

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从柠檬酸铀酰凝胶燃烧和电喷雾辅助造粒制备氮化铀

我们报道了一种新的合成路线，通过碳热还原和氮化前驱体在氩气下燃烧柠檬酸铀酰凝胶得到氮化铀。凝胶燃烧产生的粉末中，纳米UO2岛被精细地分散在碳基体中。然后通过一种新型的电喷雾辅助造粒方法对该粉末进行造粒，最后在氮气气氛下碳热还原得到单相UN。然后通过火花等离子烧结将UN颗粒致密到高密度，而传统的无压烧结导致密度低。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.