A strategy for imparting radiation resistance to dilute alloys using synergistic solutes

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-07-29 DOI:10.1016/j.jnucmat.2025.156070

Soumyajit Jana, Robert S. Averback, Pascal Bellon

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引用次数: 0

Abstract

A novel approach for imparting radiation resistance to dilute alloys is proposed whereby two synergistic solute species are employed, a first one, solute B, that binds strongly to vacancies and a second one, solute C, that binds to solute B and is also a slow diffuser in solvent A. This combination results in B-C solute clusters that are immobile traps for vacancies. These traps promote point-defect recombination over irradiation doses far beyond that achievable in binary alloys, where solutes that strongly bind to vacancies are typically fast diffusers and thus quickly removed from grain interiors by radiation-induced segregation. A parametric study, performed using atomistic kinetic Monte Carlo simulations with realistic metallic solute properties in Cu, reveals that alloy stability under irradiation derives largely from the formation of mixed B-C solute clusters comprised of 10 or more atoms. The solute loss at sinks, moreover, is found to follow stretched exponentials, with the most promising alloys corresponding to values of the stretch exponent

β

approaching 0.5. The effects of irradiation dose rate and grain size are discussed using simple scaling relationships. Lastly, the approach is illustrated by identifying promising solute combinations in Cu, Ni and Al alloys.

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一种利用协同溶质增强稀合金抗辐射能力的策略

提出了一种赋予稀合金抗辐射能力的新方法，即采用两种协同溶质，第一种是溶质B，它与空位紧密结合，第二种是溶质C，它与溶质B结合，也是溶剂A中的缓慢扩散器。这种组合产生了B-C溶质团簇，它们是空位的固定陷阱。在二元合金中，与空位紧密结合的溶质通常是快速扩散器，因此通过辐射诱导的偏析可以迅速从晶粒内部移除。利用原子动力学蒙特卡罗模拟方法对Cu中真实金属溶质性质进行了参数化研究，结果表明，辐照下合金的稳定性主要来自于由10个或更多原子组成的混合B-C溶质团簇的形成。此外，发现汇处的溶质损失遵循拉伸指数，最有前途的合金对应于拉伸指数β接近0.5的值。用简单的标度关系讨论了辐照剂量率和晶粒尺寸的影响。最后，通过确定Cu， Ni和Al合金中有前途的溶质组合来说明该方法。

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.