Surface morphology evolution, microstructural response and mechanical property variation of Au-ion irradiated CrNbZrMoV, TiCrZrMoV, TiNbCrMoV, TiNbZrCrV and TiNbZrMoCr high-entropy alloy coatings

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-09-26 DOI:10.1016/j.jnucmat.2024.155430

Jiuguo Deng , Wei Zhang , Mingyang Zhou , Ziyao Long , Xi Qiu , Yi Zhou , Jijun Yang

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Abstract

In this work, the CrNbZrMoV, TiCrZrMoV, TiNbCrMoV, TiNbZrCrV and TiNbZrMoCr refractory high-entropy alloy (RHEA) coatings (1.67∼2.77 μm of thickness) were prepared by magnetron sputtering. Then, 6 MeV Au-ion irradiations with 2.5 × 10¹⁵ to 1.0 × 10¹⁶ ions/cm² fluences were performed on these coatings at 473 K, and the surface morphology, microstructure and mechanical property were investigated. The peak damage of the CrNbZrMoV, TiCrZrMoV, TiNbCrMoV, TiNbZrCrV and TiNbZrMoCr coatings under 1.0 × 10¹⁶ ions/cm² fluence are 48, 48, 44, 48 and 48 dpa, respectively. The peak Au concentration of the CrNbZrMoV, TiCrZrMoV, TiNbCrMoV, TiNbZrCrV and TiNbZrMoCr coatings under 1.0 × 10¹⁶ ions/cm² fluence are 4.27 × 10³, 4.12 × 10³, 4.13 × 10³, 4.16 × 10³ and 4.37 × 10³ appm, respectively. The surface morphology of the CrNbZrMoV, TiCrZrMoV, TiNbZrCrV and TiNbZrMoCr coatings were smoothed obviously. For BCC TiNbCrMoV coating, irradiation caused the growth of the nanocrystalline. For amorphous coatings, the crystallization occurred in the CrNbZrMoV, TiCrZrMoV and TiNbZrMoCr coatings after 2.5 × 10¹⁵ fluence irradiation (≥12 dpa), while the TiNbZrCrV coating remain mainly amorphous structure after all irradiation. It was found that irradiation induced continuous crystallization occurred not only at the surface but also in the peak damage zone of the coating, and then grew inside the irradiated region. Apparent irradiation hardening was observed in all the coatings except the TiNbZrCrV coating. The structural stability of these coatings under the current irradiation condition was discussed. Preliminary study shows that the great irradiation tolerance of amorphous TiNbZrCrV coating may be related to the lowest electronegativity difference (Δχ = 0.121) and large atomic size difference (δ = 9.042 %) that stabilize the structure and inhibit atomic diffusion, respectively. These findings provide the guidance for the development of high irradiation tolerance materials for future nuclear energy applications with great structural stability.

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金离子辐照 CrNbZrMoV、TiCrZrMoV、TiNbCrMoV、TiNbZrCrV 和 TiNbZrMoCr 高熵合金镀层的表面形貌演变、微结构响应和力学性能变化

本研究采用磁控溅射法制备了 CrNbZrMoV、TiCrZrMoV、TiNbCrMoV、TiNbZrCrV 和 TiNbZrMoCr 难熔高熵合金 (RHEA) 涂层（厚度为 1.67 ∼ 2.77 μm）。然后，在 473 K 下以 2.5 × 1015 至 1.0 × 1016 离子/cm2 的通量对这些涂层进行了 6 MeV 金离子照射，并对其表面形貌、微观结构和机械性能进行了研究。在 1.0 × 1016 离子/平方厘米的通量下，CrNbZrMoV、TiCrZrMoV、TiNbCrMoV、TiNbZrCrV 和 TiNbZrMoCr 涂层的峰值损伤分别为 48、48、44、48 和 48 dpa。在 1.0 × 1016 离子/cm2 通量下，CrNbZrMoV、TiCrZrMoV、TiNbCrMoV、TiNbZrCrV 和 TiNbZrMoCr 涂层的金浓度峰值分别为 4.27 × 103、4.12 × 103、4.13 × 103、4.16 × 103 和 4.37 × 103 appm。CrNbZrMoV、TiCrZrMoV、TiNbZrCrV 和 TiNbZrMoCr 涂层的表面形态明显平滑。对于 BCC TiNbCrMoV 涂层，辐照导致了纳米晶的生长。对于无定形涂层，CrNbZrMoV、TiCrZrMoV 和 TiNbZrMoCr 涂层在 2.5 × 1015 流强辐照（≥12 dpa）后出现结晶，而 TiNbZrCrV 涂层在所有辐照后仍以无定形结构为主。研究发现，辐照诱导的连续结晶不仅发生在涂层表面，也发生在涂层的峰值损伤区，然后在辐照区内部生长。除 TiNbZrCrV 涂层外，所有涂层都出现了明显的辐照硬化。讨论了这些涂层在当前辐照条件下的结构稳定性。初步研究表明，非晶态 TiNbZrCrV 涂层之所以具有很强的辐照耐受性，可能与最低的电负性差（Δχ = 0.121）和较大的原子尺寸差（δ = 9.042 %）有关，它们分别起到了稳定结构和抑制原子扩散的作用。这些发现为开发结构稳定的高辐照耐受性材料提供了指导，可用于未来的核能应用。

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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.