First-principles prediction of thermodynamic and mechanical properties of ZrCr2 under extreme conditions

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Hongling Zhou , Baifeng Luan , An Yan , Xiaoling Yang , Congqing Liu , Xuyang Liu , Chunrong Xu , Chao Sun , Haibo Ruan , Weijiu Huang , Korukonda L. Murty
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引用次数: 0

Abstract

The cubic C15 and hexagonal C14/C36 phases of ZrCr2 are typical phases formed in the newly developed Cr-coated Zr alloy cladding, and their formation and transformation significantly affect the system's service performance. However, their crystal structures and associated thermodynamic and mechanical properties under high temperatures and pressures are not fully elucidated. This work comprehensively explores the phase stability, thermodynamic, and mechanical properties of these three ZrCr2 polymorphs over a temperature range from 0 to 2500 K and pressure from 0 to 30 GPa using first-principles calculations. The calculated lattice parameters agree well with experimental values. It is confirmed that C15 is the stable phase at low temperatures, C36 serves as an intermediate phase, and C14 is relatively prevalent at high temperatures. Above 10 GPa, C14 is no longer stable in the temperature range studied. Temperature and pressure significantly influence the thermodynamic and mechanical properties of the three ZrCr2 phases. All three phases are ductile, but their ductility decreases as temperature rises and pressure decreases, accompanied by volume expansion, suggesting that ZrCr2 formation during a loss of coolant accident could significantly increase the risk of cracking. These results advance our understanding of the thermodynamic and mechanical behavior of the ZrCr2 phases under high temperatures and pressures, providing essential insights for designing high-performance Cr-coated Zr alloy cladding in nuclear engineering.
ZrCr2在极端条件下热力学和力学性能的第一性原理预测
ZrCr2的立方相C15和六边形相C14/C36是新研制的cr包覆Zr合金熔覆层中形成的典型相,它们的形成和转变对系统的使用性能有显著影响。然而,它们的晶体结构及其在高温高压下的热力学和力学性能尚未完全阐明。本研究利用第一性原理计算,全面探讨了这三种ZrCr2多晶在0 ~ 2500k温度范围和0 ~ 30gpa压力下的相稳定性、热力学和力学性能。计算得到的晶格参数与实验值吻合较好。经验证,C15是低温稳定相,C36是中间相,C14在高温下较为普遍。在10gpa以上,C14在所研究的温度范围内不再稳定。温度和压力对ZrCr2三相的热力学和力学性能有显著影响。这三种相都具有延展性,但随着温度升高和压力降低,它们的延展性会降低,并伴随着体积的膨胀,这表明在冷却剂丢失事故中形成的ZrCr2可能会显著增加开裂的风险。这些结果促进了我们对高温高压下ZrCr2相热力学和力学行为的理解,为核工程中高性能cr包覆Zr合金包层的设计提供了重要的见解。
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
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.
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