Microstructure and properties controlling of Al-xGd alloys for thermal neutron absorbing

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-10-10 DOI:10.1016/j.jnucmat.2024.155447
Zixie Wang , Jie Pan , Ao Liu , Li Zhang , Zeyuan Sun , Zhen Wang , Jun Li , Xueshan Xiao
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Abstract

A novel lightweight thermal neutron absorbing Al-xGd alloy (x = 2.5, 5, and 10 wt.%) with tunable mechanical properties was fabricated by induction melting followed by a rolling process and an annealing treatment. During solidification, the Al3Gd phase predominantly formed and was distributed along grain boundaries. Cold rolling crushed and redistributed the Al3Gd phase throughout the matrix. Furthermore, the large deformation imposed on the material during cold rolling enhanced the work hardening effect and promoted dynamic recrystallization. The load transfer strengthening effect was influenced by the size, volume fraction, and distribution of the second phase. The spheroidization of the second phase increased rapidly and then remained stable during 5000 h long-term aging at 400 °C. The thermal neutron absorbing performance of the Al-5Gd alloy is comparable to the 30 %B4C/Al composite evaluated by Monte Carlo simulations. Furthermore, Al-5Gd alloy exhibited higher plasticity (>20 %). This novel Al-xGd alloy is a promising candidate for future lightweight thermal-neutron-absorbing materials.

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用于热中子吸收的 Al-xGd 合金的微观结构和性能控制
通过感应熔炼、轧制过程和退火处理,制造出了具有可调机械性能的新型轻质热中子吸收 Al-xGd 合金(x = 2.5、5 和 10 wt.%)。在凝固过程中,主要形成了 Al3Gd 相,并沿晶界分布。冷轧将 Al3Gd 相压碎并重新分布到整个基体中。此外,冷轧过程中施加在材料上的大变形增强了加工硬化效应,促进了动态再结晶。载荷传递强化效应受第二相的尺寸、体积分数和分布的影响。第二相的球化迅速增加,并在 400 °C 下长期时效 5000 小时后保持稳定。Al-5Gd 合金的热中子吸收性能与蒙特卡罗模拟评估的 30 %B4C/Al 复合材料相当。此外,Al-5Gd 合金还表现出更高的塑性(20%)。这种新型 Al-xGd 合金是未来轻质热中子吸收材料的理想候选材料。
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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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