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.
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.