用铌和钼作为氧化还原添加剂缓冲二氧化铀燃料的氧活性

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-03-01 Epub Date: 2025-02-03 DOI:10.1016/j.jnucmat.2025.155647
Philippe Garcia , Erwin Douguet-Bronnec , Franck Fournet-Fayard , Florian Le Hello , Xavière Iltis , Nicolas Tarisien , Jacques Fouletier , Marlu Cesar Steil
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引用次数: 0

摘要

我们证明,通过在制造过程中加入具有强氧化还原活性的添加剂来控制氧化铀燃料的氧活性是可能的。为此,我们研究了三种多晶二氧化铀样品的宏观电化学性能,第一种样品同时含有钼和二氧化钼,第二种样品含有二氧化铌,最后一种样品除杂质外不含任何添加剂。在实验期间,样品受到还原和随后氧化的气氛相对于氧分压,其中氧化和还原形式的添加剂处于平衡状态。原位监测样品的电化学反应表明,氧化还原对的存在,无论是涉及铌或钼显著改变了二氧化铀固体的氧活性。高温测量前后的扫描电镜(SEM)、电子背散射衍射(EBSD)和能量色散x射线分析(EDX)证实了原位数据:最终的微观结构表明,含钼和含铌样品的电化学活性分别由Mo/MoO2和NbO2/Nb2O5偶对控制。
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Buffering the oxygen activity of uranium dioxide fuels using niobium and molybdenum as redox additives
We demonstrate that it is possible to control the oxygen activity of a uranium oxide fuel by incorporating additives during the manufacturing process that have a strong redox activity. To this end, we have studied the macroscopic electrochemical properties of three polycrystalline uranium dioxide samples, the first containing both molybdenum and molybdenum dioxide, the second containing niobium dioxide and the last containing no additives other than impurities. During experiments, samples were subjected to reducing and subsequently oxidizing atmospheres with respect to the oxygen partial pressure at which the oxidized and reduced forms of the additives are in equilibrium. In situ monitoring of the electrochemical response of the samples reveals that the presence of redox couples involving either niobium or molybdenum significantly modifies the oxygen activity of a uranium dioxide solid. Scanning Electron Microscopy (SEM), Electron Back-Scatter Diffraction (EBSD) and Energy Dispersive X-ray analysis (EDX) prior to and following the high temperature measurements, confirm the in situ data: the final microstructure purports to show that the electrochemical activity is controlled by the Mo/MoO2 and the NbO2/Nb2O5 couples for the molybdenum and niobium containing samples respectively.
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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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