Annealing-induced microstructure and mechanical property evolution of helium-irradiated Cr coatings

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

Journal of Nuclear Materials Pub Date : 2025-04-24 DOI:10.1016/j.jnucmat.2025.155854

Qining Zheng , Shuqin Wen , Mingju Chen , Ce Zheng , Guanghai Bai , Jinshan Li , Biao Chen

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Abstract

Post-irradiation annealing (PIA) is a highly effective approach for investigating the impacts of irradiation temperature. In this work, annealing at 350–800 °C was conducted on helium ion irradiated (300 keV, 6.85 × 10¹⁵ ions/cm²) chromium coatings, and the impact of annealing temperature on irradiation defects and mechanical properties of chromium was investigated. A critical temperature threshold of 700 °C (0.45 T_m) was identified, beyond which helium bubbles exhibited a pronounced transition in coarsening behavior: gradual growth below 700 °C transitioned to rapid coarsening dominated by migration-coalescence mechanisms at higher temperatures. Concurrently, grain boundaries emerged as preferential defect sinks, facilitating bubble nucleation and growth. The swelling rate of the coating is primarily governed by bubble size and increases with temperature. Dislocation loops displayed coevolution with helium bubbles, mirroring temperature-dependent growth trends. Irradiation hardening primarily originated from dislocation pinning by both loops and bubbles. Depth-resolved nanoindentation analysis via the Nix-Gao model quantified intrinsic hardness gradients, revealing deviations from theoretical predictions attributed to unaccounted defects below 2 nm and grain-coarsening effects.

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氦辐照Cr涂层退火组织及力学性能演变

辐照后退火（PIA）是研究辐照温度影响的有效方法。在这项工作中，对氦离子（300 keV， 6.85 × 10¹5离子/cm²）辐照的铬涂层进行了350-800℃的退火，并研究了退火温度对铬的辐照缺陷和力学性能的影响。在700°C （0.45 Tm）的临界温度阈值下，氦气泡的粗化行为发生了明显的转变：在700°C以下逐渐长大，在更高温度下以迁移-聚结机制为主，转变为快速粗化。同时，晶界作为优先缺陷汇出现，有利于气泡的形核和生长。涂层的膨胀率主要由气泡大小决定，并随温度的升高而增大。位错环与氦泡共同演化，反映了温度依赖的生长趋势。辐照硬化主要是由位错钉住环和气泡引起的。通过Nix-Gao模型进行深度分辨纳米压痕分析，量化了固有硬度梯度，揭示了2纳米以下未解释缺陷和晶粒粗化效应与理论预测的偏差。

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.