First-principles-based equilibrium Monte Carlo simulations of Cr-rich cluster stability in Fe–Cr–Al alloys: Effects of Al content and vacancies on the transition from promotion to suppression
IF 3.2 2区 工程技术Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
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引用次数: 0
Abstract
Understanding the formation and stability of Cr-rich clusters (CrRCs) is essential for developing accident-tolerant oxide dispersion-strengthened Fe–Cr–Al alloys. This study employs first-principles-based equilibrium Monte Carlo simulations to quantitatively evaluate the effects of Al concentration and irradiation-induced vacancies on CrRC formation and atomic-scale structural behavior. Statistical metrics such as cluster size distribution, radial distribution functions, and short-range order parameters were used. With increasing Al content, CrRC formation exhibited a non-monotonic trend, peaking near 12 at.% Al. This aligns with prior static energy calculations but additionally captures Al segregation at CrRC–matrix interfaces and, at high Al concentrations, apparent Al incorporation within the cluster region causing structural diffusion and increased lattice displacement, which negatively impacts stability. Vacancies showed little direct effect on CrRC formation but strongly interacted with Al, co-segregating near interfaces. This Al–vacancy co-segregation may influence interface stability and diffusion under irradiation. These findings deepen atomic-scale understanding of CrRC behavior under thermal and irradiation conditions, providing foundational data for designing radiation-resistant Fe–Cr–Al alloys and supporting future mesoscale modeling.
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.