Effect of hydrogen on oxidative dissolution of epsilon particles-doped UO2 pellets under carbonate condition with hydrogen peroxide

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
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Abstract

The epsilon particles that result from nuclear fission of UO2 fuel possess both advantages and disadvantages from a spent nuclear fuel (SNF) management perspective. In this study, the effect of epsilon particles, namely Ru, Mo, and Pd, inherent in simulated UO2 pellets is examined. Various analytical methods have been used to explore the changes in the structural, surface, and electrochemical properties of which contain epsilon particles. A notable finding is that the epsilon particles are not evenly distributed and tend to clump together, transforming into a metallic state after sintering, as detailed in the X-ray diffraction analyses. Energy-dispersive X-ray spectroscopy analyses highlight interesting aspects of the distribution of elements, especially the disappearance of Pd during sintering, which is likely due to its high vapor pressure. Although the lattice structure of UO2 remains unchanged, the sizes of the grains and pores visibly change, which may influence the tendency of UO2 pellet-cracking. Despite the addition of the epsilon particles, the electrical conductivity analyses show no significant changes, suggesting that they act as minor impurities without affecting the structural lattice. However, their possible role as catalysts in electrochemical reactions opens new and interesting areas that require thorough investigation. Moreover, examining the anodic dissolution under various conditions provides detailed insights into UO2 dissolution and oxidation, revealing how epsilon particles subtly influence the oxidative dissolution process. This study clarifies the basic interactions and effects of epsilon particles in UO2 pellets and broadens the path for a deeper understanding and improvement of nuclear fuel matrices and steering advancements in the safe and effective use of nuclear energy.

氢气对碳酸盐条件下过氧化氢氧化溶解ε粒子掺杂的二氧化钛颗粒的影响
从乏核燃料(SNF)管理的角度来看,二氧化铀燃料核裂变产生的ε粒子有利有弊。本研究考察了模拟二氧化铀颗粒中固有的ε粒子(即Ru、Mo和Pd)的影响。使用了各种分析方法来探讨含有ε粒子的颗粒在结构、表面和电化学特性方面的变化。一个值得注意的发现是,ε粒子分布不均匀,往往聚集在一起,在烧结后转变为金属状态,这在 X 射线衍射分析中有详细说明。能量色散 X 射线光谱分析突出显示了元素分布的有趣方面,特别是钯在烧结过程中消失,这可能是由于其蒸汽压较高。虽然二氧化铀的晶格结构保持不变,但晶粒和孔隙的大小发生了明显变化,这可能会影响二氧化铀球团的开裂趋势。尽管加入了ε粒子,但电导率分析却没有显示出明显的变化,这表明ε粒子作为次要杂质不会影响晶格结构。不过,它们在电化学反应中可能扮演的催化剂角色开辟了新的有趣领域,需要进行深入研究。此外,通过研究各种条件下的阳极溶解,可以详细了解二氧化钛的溶解和氧化过程,揭示ε粒子如何微妙地影响氧化溶解过程。这项研究阐明了ε粒子在二氧化铀球团中的基本相互作用和影响,为深入了解和改进核燃料基质以及引导核能安全有效利用的进步拓宽了道路。
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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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