开发用于固定模拟四价锕系元素的 ZrSiO4 硼硅酸盐玻璃陶瓷

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

Journal of Nuclear Materials Pub Date : 2024-10-20 DOI:10.1016/j.jnucmat.2024.155472

Hui Dan, Yihang Li, Bingbing Bao, Jiajing Li, Jiyuan Guo, Yi Ding

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引用次数: 0

摘要

开发高效固定锕系元素的新基体对核能的可持续发展具有重要意义。本文制备了新型 ZrSiO4 硼硅酸盐玻璃陶瓷（Z-B），用于固定模拟四价锕系元素铈（Ce）。研究了铈含量对所获得的 Z-B 的相变和微观结构的影响，并评估了铈的负载能力极限。结果表明，获得了具有高 ZrSiO4 相（91 wt%）的 Z-B 玻璃陶瓷。由于 ZrSiO4 和硼硅酸盐玻璃相的协同作用，所获得的 Z-B 中 Ce 的负载能力极限高达 12%。此外，所获得的 Z-B 废料具有优异的水耐久性。这项工作的结果表明，Z-B 具有良好的负载能力和水耐久性，是固定四价锕系元素的潜在基质。

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Development of ZrSiO4-borosilicate glass-ceramics for immobilization of simulated tetravalent actinides

Developing new matrix for efficient actinides immobilization is of great significance for the sustainable development of nuclear energy. Herein, novel ZrSiO₄-borosilicate glass-ceramics (Z-B) were prepared for immobilization of cerium (Ce) as the simulated tetravalent actinides. The effect of Ce content on the phase transformation and microstructure of the obtained Z-B was investigated, and the loading capacity limit of Ce was evaluated. The results demonstrated that Z-B glass-ceramics with high ZrSiO₄ phase (91 wt%) was obtained. Owing to the synergistic effect of ZrSiO₄ and borosilicate glass phases, the loading capacity limit of Ce in the obtained Z-B reached up to 12 at%. Furthermore, the obtained Z-B waste forms exhibited excellent aqueous durability. The results of this work demonstrated that the Z-B is potential matrix for immobilization of tetravalent actinides due to their good loading capacity and aqueous durability.

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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.