Effect of grain boundaries on the helium degradation mechanisms of alloy 800H: A molecular dynamics study

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-09-19 DOI:10.1016/j.jnucmat.2024.155395
I. Cheik Njifon, E. Torres
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Abstract

Alloy 800H is currently used as structural material in light-water cooled nuclear reactors, and it is also considered as candidate materials for various advanced reactor designs. Under operation, the exposure of alloy 800H to neutron irradiation results in the formation of helium (He), mainly from Ni by the transmutation reaction (n, α). In this work, we present a molecular dynamics (MD) simulation study of the behavior and effects of He on the microstructure and mechanical properties of alloy 800H. Our results show that the population of clusters made of 5 to 9 He atoms is nearly constant throughout the simulation time (10 ns), while the population of larger clusters increases as the simulation time increases. The growth of clusters is controlled by either the dissociation and diffusion of smaller clusters towards nearby larger clusters or the merging of larger clusters initially located nearby to each other. A significant accumulation of He is observed at the grain boundaries (GB), while a depletion zone is found at the neighboring regions. As a result, the density of He cluster is significantly higher at the GBs as compared to the intra-granular regions. The nucleation and growth of He clusters also results in the formation of Frenkel pairs (FP), whose associated self-interstitial atoms (SIA) agglomerate into interstitial clusters in the alloy 800H matrix. As a consequence, dislocation segments, mostly of the Shockley type, are generated in the microstructure, and often located next to He clusters. The combination of the aforementioned defect structures and the high density of He clusters at the GBs results in a substantial degradation of the mechanical properties of alloy 800H single crystal and bicrystals.

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晶界对合金 800H 的氦降解机制的影响:分子动力学研究
合金 800H 目前用作轻水冷却核反应堆的结构材料,也被视为各种先进反应堆设计的候选材料。在运行过程中,合金 800H 受中子辐照后会形成氦(He),主要是由 Ni 通过嬗变反应(n,α)形成的。在这项工作中,我们对 He 对合金 800H 的微观结构和机械性能的行为和影响进行了分子动力学(MD)模拟研究。我们的结果表明,在整个模拟时间(10 ns)内,由 5 到 9 个 He 原子组成的团簇数量几乎是恒定的,而较大团簇的数量则随着模拟时间的延长而增加。簇群的增长受控于较小簇群的解离和向附近较大簇群的扩散,或最初位于附近的较大簇群的合并。在晶粒边界 (GB) 观察到 He 的大量积累,而在邻近区域则发现了耗竭区。因此,与晶粒内部区域相比,晶粒边界区域的氦团密度要高得多。He 簇的成核和生长还导致弗伦克尔对(FP)的形成,其相关的自间隙原子(SIA)在合金 800H 基体中聚集成间隙簇。因此,在微观结构中产生了位错段,主要是肖克利型位错段,通常位于 He 簇旁边。上述缺陷结构与 GB 上高密度的 He 簇相结合,导致合金 800H 单晶和双晶的机械性能大幅下降。
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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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