Combined effects of radiation damage and He accumulation in Y2Ti2O7 borosilicate glass-ceramic composites

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

Journal of Nuclear Materials Pub Date : 2025-08-21 DOI:10.1016/j.jnucmat.2025.156103

Menghan Jiang , Anamul Haq Mir , Mounib Bahri , Yingjie Zhang , Keith Arnold , Nigel Browning , Karl Whittle , Maulik Patel

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引用次数: 0

Abstract

Glass-ceramics have been regarded as potential nuclear wasteforms for immobilization of high-level waste. Understanding material modifications due to combined damage by α-decay is the key in predicting long-term evolution of wasteforms. 10 keV in-situ helium implantation experiments were carried out on TEM specimens extracted from Y₂Ti₂O₇ glass-ceramic samples pre-irradiated with 7 MeV Au to understand the kinetics of helium bubble evolution, showing that the accumulation of He can lead to the nucleation of helium bubbles within the amorphous Y₂Ti₂O₇ ceramic phase at a critical concentration of 3.4 at.%. Structural modifications by Au irradiation were characterized using grazing-incidence x-ray diffraction (GIXRD) and scanning transmission electron microscopy (STEM). The STEM results revealed that complete amorphization of the pyrochlore structure occurred at

5 \times 10^{14}

Au/cm². A phase transformation to defect-fluorite structure is also observed at the irradiated interface. Besides, a potential Y-rich phase was identified within the glass matrix, which likely originated from the effects of irradiation.

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辐射损伤与He在Y2Ti2O7硼硅酸盐玻璃陶瓷复合材料中的复合效应

微晶玻璃被认为是固定化高放废物的潜在核废料形式。了解α-衰变复合损伤引起的材料变化是预测废物形态长期演变的关键。对经7 MeV Au预辐照的Y2Ti2O7玻璃陶瓷样品进行了10 keV原位氦注入实验，了解了氦气泡演化动力学，结果表明，在临界浓度为3.4 at.%时，He的积累可导致非晶Y2Ti2O7陶瓷相内氦气泡成核。利用掠入射x射线衍射（GIXRD）和扫描透射电镜（STEM）对Au辐照后的结构修饰进行了表征。STEM结果显示，在5×1014 Au/cm2下，焦绿石结构完全非晶化。在辐照界面处还观察到向缺陷萤石结构的相变。此外，在玻璃基体中发现了一个潜在的富y相，这可能是由于辐照的影响。

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.