Study on the mechanical properties at high temperatures and relevant mechanism of beryllium oxide ceramics

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

Journal of Nuclear Materials Pub Date : 2025-04-08 DOI:10.1016/j.jnucmat.2025.155813

Xiang-wen Zhou, Jin Zhang, Ming-dong Hou, Shouchi Zhang, Kaihong Zhang, Rongzheng Liu, Bing Liu, Yaping Tang, Lei Shi

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引用次数: 0

Abstract

In recent years, beryllium oxide (BeO) ceramics have been reconsidered for application in micro nuclear reactors. The applications of BeO ceramics in micro nuclear reactors are mainly as neutron moderator, neutron reflector material or nuclear fuel pellet matrix material. When used in these reactors, BeO is often subjected to extreme environments. Therefore, it is necessary to master the high temperature mechanical properties of BeO. In this paper, the mechanical properties of BeO ceramics at high temperature were studied experimentally, which shows a trend that first increasing, then decreasing and at last increasing again. Besides, the corresponding mechanism was discussed and it was concluded that the glass phase between the grains of BeO is the key factor affecting its high temperature strength. The mechanism was verified by molecular dynamics (MD) simulation. This paper is of great significance for the application of BeO ceramics.

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氧化铍陶瓷的高温力学性能及其机理研究

近年来，氧化铍（BeO）陶瓷在微核反应堆中的应用得到了重新考虑。BeO陶瓷在微核反应堆中的应用主要是作为中子慢化剂、中子反射材料或核燃料球团基体材料。当在这些反应器中使用时，BeO经常受到极端环境的影响。因此，有必要掌握BeO的高温力学性能。本文对BeO陶瓷的高温力学性能进行了实验研究，结果表明BeO陶瓷的力学性能表现出先升高后降低再升高的趋势。并对其机理进行了探讨，认为BeO晶粒间的玻璃相是影响其高温强度的关键因素。通过分子动力学（MD）模拟验证了其机理。本文对BeO陶瓷的应用具有重要意义。

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.