Optical dilatometry and sintering studies of Cr2O3-doped UO2

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Sarah Vallely , Ritesh Mohun , David W. Williams , P. John Thomas , Mattias Puide , David T. Goddard , William E. Lee , Simon C. Middleburgh
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引用次数: 0

Abstract

Optical dilatometry has been used to study the sintering behaviour of Cr2O3-doped UO2 and such observations have been compared to undoped UO2, enabling a visual and measurable comparison of their behaviour during this important manufacturing step. Sintering UO2 and Cr2O3-doped UO2 pellets at different temperatures allowed for grain nucleation and growth to be assessed. Optical dilatometry was implemented to visually assess differences in the densification of UO2 and Cr2O3-doped UO2. The rate of sintering and extent of shrinkage was found to be higher for the doped pellet, with the Cr2O3-doped pellet decreasing in volume by ∼40 %, compared to only ∼20 % for the undoped pellet. The temperature at which shrinkage commenced was also approximately 100 – 200 °C lower for the doped sample than for the undoped variant. This indicates that there is a difference between the sintering processes of the two systems. The possible contribution of the CrUO4 secondary phase to large grain growth has also been examined through Differential Scanning Calorimetry (DSC) in reducing conditions. A change occurring at approximately 1250 °C for CrUO4 was observed. This temperature corresponds to the end of shrinkage and start of grain growth for Cr2O3-doped UO2 pellets, as shown in the optical dilatometry experiments, which could be indicative of the commencement of the large-grain growth process.
cr2o3掺杂UO2的光学膨胀测量和烧结研究
光学膨胀法已被用于研究cr2o3掺杂UO2的烧结行为,并将这些观察结果与未掺杂的UO2进行了比较,从而在这一重要的制造步骤中对它们的行为进行了视觉和可测量的比较。在不同温度下烧结UO2和cr2o3掺杂的UO2球团,可以评估晶粒的成核和生长。采用光学膨胀法来直观地评估UO2和cr2o3掺杂UO2的密度差异。发现掺杂球团的烧结速率和收缩程度更高,与未掺杂球团相比,掺杂cr2o3球团的体积减少了约40%。在收缩开始时,掺杂样品的温度也比未掺杂样品低约100 - 200℃。这表明两种体系的烧结工艺存在差异。在还原条件下,通过差示扫描量热法(DSC)研究了cro4二次相对大晶粒生长的可能贡献。在大约1250°C时,观察到CrUO4发生变化。该温度对应于cr2o3掺杂UO2球团的收缩结束和晶粒生长的开始,如光学膨胀实验所示,这可能预示着大晶粒生长过程的开始。
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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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