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.
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.