对单片铀钼燃料板制造历史的评述

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Jason L․ Schulthess , Walter․ J․ Williams , Jan-Fong Jue , R․ Bruce Nielson , John Merickel , Yucheng․ Fu
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引用次数: 0

摘要

整体铀钼合金燃料的制造,特别是那些为高性能研究和试验反应堆开发的燃料,始于本世纪初。主要的燃料形式是在覆有锆的薄箔和包裹在铝-6061包层中的含10%钼的铀合金。多年来,该工艺随着不同类型的铸造,热处理,轧制计划和包层应用而发展。本文综述了这些制造工艺的历史及其对微结构和燃料膨胀性能的影响。尽管使用了各种制造方法,但我们发现制造变化与燃料膨胀之间的相关性很小。制造变化和燃料膨胀之间的不敏感关系主要是由于铸造过程中形成的不均匀组织和轧制过程中发生的晶粒细化。我们得出的结论是,我们所研究的制造工艺产生了相似的微观结构,表明燃料微观结构对所评估的制造参数有些不敏感。然而,相对较少的历史数据,如粒度数据,限制了这种分析。最近制造的材料,例如正在进行的辐照实验中的材料,Mini-Plate-1和Mini-Plate-2,也被排除在本分析之外,并打算单独审查。研究发现,燃料微观结构对制造参数有些不敏感,但考虑到数据和燃料膨胀观察的不确定性,并不意味着任何制造方法都是可以接受的。例如,在历史上的制造工作中,只有电弧熔化和真空感应熔化铸造工艺被探索过。研究结果不应推断到其他铸造工艺。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A critical review of the history of fabricating monolithic U-Mo fuel plates
The fabrication of monolithic uranium-molybdenum alloy fuels, specifically those developed for high-performance research and test reactors, began in the early 2000s. The primary fuel form consists of uranium alloyed with 10-wt% molybdenum in a thin foil coated with zirconium and encapsulated in aluminum-6061 cladding. Over the years, the process has evolved with different types of casting, heat treatments, rolling schedules, and cladding applications. This review examines the history of these fabrication processes and their impact on microstructure and fuel-swelling performance.
Even though various fabrication methods were used, we found little correlation between fabrication variation and fuel swelling. This insensitive relationship between fabrication variation and fuel swelling is primarily due to inhomogeneous microstructures that formed during casting and grain refinement that occurred during rolling. We conclude that the fabrication processes we examined produced similar microstructures, indicating that the fuel microstructure is somewhat insensitive to the fabrication parameters evaluated. However, the relatively small amount of historic data, such as those for grain sizes, limited this analysis. More recently fabricated materials, such as those from ongoing irradiation experiment, Mini-Plate-1 and Mini-Plate-2, were also excluded from this analysis and are intended to be reviewed separately. The findings, that fuel microstructure is somewhat insensitive to the fabrication parameters, do not imply that any fabrication method is acceptable, given the uncertainties in data and fuel-swelling observations. For example, only arc melting and vacuum induction melting casting processes were previously explored in the historic fabrication efforts. The findings should not be extrapolated to other casting processes.
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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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