工业化生产的钚处置 MOX 演示

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-10-23 DOI:10.1016/j.jnucmat.2024.155477
Claire L. Corkhill , Latham T. Haigh , Lewis R. Blackburn , Luke T. Townsend , Daniel J. Bailey , Lucy M. Mottram , Amber R. Mason , Max R. Cole , Thierry Gervais , Genevieve Kerboul
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引用次数: 0

摘要

安全可靠地管理民用分离钚是英国政府和国家原子能机构的优先事项。解决这一问题的一个潜在方案是考虑制造一种改进型混合氧化物(MOX)燃料,包括分散在二氧化铀基体中的二氧化铀,并掺入适当的中子吸收元素以保持临界控制。作为了解工业上相关的、经过验证的 MOX 燃料制造工艺能否为基于 MOX 的钚分散基质的生产提供潜在途径的第一步,奥拉诺公司在法国 MELOX 设施的 CDA 车间制备了一系列掺钆的二氧化铀颗粒。对密度、形态(晶粒大小和孔隙率)、钆分布和钆掺入机制进行了定量表征。研究发现,所生产的材料具有很高的可重复性,密度和形态相似,与未经过辐照的 UOX 和 MOX 燃料相似,与所研究的变量无关。钆的分布方式与未经过辐照的 MIMAS(MIcronisation of a MASter Blend)MOX 燃料中二氧 化钚的分布方式相似,并确定了 Gd2O3 和二氧铀之间存在固溶体的证据,这从 GDF 关闭后临界控制的角度来看是有利的。由于烧结反应性的原因,粉末来源对钚沉积 MOX 粒子的最终特性影响最大;不过,这些差异很小。这些结果是在政策允许的情况下,向全面制造适合固定和处置全球乏燃料发展基金中分离的二氧化铀的陶瓷迈出的充满希望的一步。
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Demonstration of industrially-fabricated plutonium disposition MOX
The safe and secure management of civil separated plutonium is a UK government and NDA priority. One potential solution to address this considers the manufacture of a modified version of mixed oxide (MOX) fuel, comprising PuO2 dispersed within a UO2 matrix and doped with a suitable neutron absorbing element to maintain criticality control. As an initial step to understand whether an industrially-relevant, proven MOX fuel fabrication process could offer a potential route to the production of a Pu-disposition matrix based on MOX, a series of Gd-doped UO2 pellets were prepared by Orano at the CDA workshop of the MELOX facility in France. Characterisation was performed to quantify the density, morphology (grain size and porosity), Gd distribution and Gd incorporation mechanism. It was found that the materials produced were highly reproducible and similar in density and morphology, irrespective of the variables investigated, and similar to unirradiated UOX and MOX fuel. Gd was distributed in a similar manner to the distribution of PuO2 in unirradiated MIMAS (MIcronisation of a MASter Blend) MOX fuel and evidence for the existence of a solid solution between Gd2O3 and UO2 was ascertained, which could be viewed as favourable from a GDF post-closure criticality control perspective. The source of the powder had the greatest effect on the final characteristics of the Pu-disposition MOX pellets, due to sintering reactivity; however, these differences were minor. These results are a promising step towards the full-scale manufacture of ceramics suitable for the immobilisation and disposition of separated PuO2 in a GDF, should policy dictate.
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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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