复杂微结构中汇强度的计算

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

Journal of Nuclear Materials Pub Date : 2025-07-08 DOI:10.1016/j.jnucmat.2025.156021

T. Jourdan , G. Adjanor

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引用次数: 0

摘要

提出了一种计算包含多种汇类型的复杂微结构中汇强度的方法，其中一些汇类型可能是移动的。它是基于缺陷平均寿命的估计和缺陷被不同的汇吸收的比例。作为一种应用，用物体动力学蒙特卡罗方法计算了含有空位和位错或晶界的微结构中自间隙原子的汇强度。研究了自间隙原子从一维扩散到三维扩散的转变以及空位迁移率的作用。多汇效应对汇强度显示存在于所有汇，但仅在自间隙原子和空位的特定扩散机制中。对已有的沉降强度表达式进行了讨论，提出了新的沉降强度表达式。

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Computation of sink strengths in complex microstructures

A method is proposed for calculating sink strengths in complex microstructures, containing several sink types, some of which may be mobile. It is based on the estimation of mean lifetime of defects and on the fraction of defects absorbed by the different sinks. As an application, sink strengths for self-interstitial atoms are calculated with object kinetic Monte Carlo in microstructures containing vacancies and dislocations or grain boundaries. The transition from one-dimensional to three-dimensional diffusion of self-interstitial atoms and the role of vacancy mobility are investigated. Multiple-sink effects on sink strengths are shown to be present for all sinks, but only in specific diffusion regimes of self-interstitial atoms and vacancies. Results are discussed in light of existing expressions of sink strengths, and new expressions are proposed.

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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.