掺杂UO2的球环等双轴弯曲试验统计断裂行为

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-04-01 Epub Date: 2025-02-25 DOI:10.1016/j.jnucmat.2025.155713
Adrianna E. Lupercio , Tashiema L. Ulrich , Andrew T. Nelson , Brian J. Jaques
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引用次数: 0

摘要

金属氧化物掺杂剂,如钛和铬氧化物,已经引起了相当大的关注,因为它们有可能增加UO2燃料的晶粒尺寸(≥30µm),据称可以增强反应堆运行期间的裂变气体潴留。燃料断裂行为对燃料性能有显著影响,因此了解晶粒尺寸和掺杂量对UO2燃料断裂的影响具有重要意义。在UO2颗粒中掺杂0.1 wt% TiO2和0.3 wt% Cr2O3来改变密度和晶粒尺寸。电感耦合等离子体质谱法测量了烧结前后的掺杂水平。x射线衍射通过Rietveld细化揭示了晶格变化和微应变。场发射扫描电镜测定TiO2掺杂的晶粒尺寸约为30µm, Cr2O3掺杂的晶粒尺寸约为7µm。每个数据集对30多个样本进行横向断裂强度测试,以获得特征强度和威布尔模量。结果表明,0.1 wt% TiO2掺杂UO2与未掺杂UO2的断裂强度无统计学差异,而0.3 wt% Cr2O3掺杂UO2的断裂强度下降了20%。与未掺杂UO2相比,掺杂UO2样品的威布尔模量降低,表明断裂强度的散射增加。本研究结果表明,在UO2中掺杂钛和氧化铬,无论晶粒大小,都会诱发残余应力,降低断裂强度,增加断裂行为的可变性。
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Statistical fracture behavior of doped UO2 using a ball-on-ring equibiaxial flexure test method
Metal oxide dopants, such as titanium and chromium oxides, have garnered considerable attention for their potential to increase grain size (≥ 30 µm) in UO2 fuel, purportedly enhancing fission gas retention during reactor operation. Fuel performance is significantly impacted by fuel fracture behavior, so it is important to understand the effects of enhanced grain size and dopant content on UO2 fuel fracture. UO2 pellets were doped with 0.1 wt% TiO2 and 0.3 wt% Cr2O3 to alter density and grain size. Inductively coupled plasma mass spectroscopy measured dopant levels pre- and post-sintering. X-ray diffraction revealed lattice changes and microstrain via Rietveld refinement. Field emission scanning electron microscopy determined grain sizes of approximately 30 µm for TiO2 doping and 7 µm for Cr2O3 doping. Transverse rupture strength tests were performed on over 30 samples per dataset to obtain characteristic strength and Weibull modulus. Results indicate no statistical difference in fracture strength between 0.1 wt% TiO2 doped UO2 and undoped UO2, while 0.3 wt% Cr2O3 doped UO2 exhibited a 20% decrease in fracture strength. Doped UO2 samples also showed reduced Weibull modulus compared to undoped UO2, suggesting increased scatter in fracture strength. This study's findings suggest that titanium and chromium oxide doping in UO2, regardless of grain size, induce residual stresses, decreasing fracture strength and increasing variability in fracture behavior.
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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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