Fe2O3掺杂UO2在还原气氛下烧结的研究

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-03-01 Epub Date: 2025-02-07 DOI:10.1016/j.jnucmat.2025.155684
Tashiema L. Ulrich , Tyler L. Spano , Luke Sadergaski , Ashley E. Shields , Eddie Lopez-Honorato , Grant Helmreich , Benjamin T. Manard , Jason Harp , Andrew T. Nelson
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引用次数: 0

摘要

含有微量过渡金属添加剂的核燃料对于引入有意签名以加速核取证具有潜在的意义。在这项工作中,我们研究了在UO2中加入微量Fe2O3形式的铁对微观结构、晶粒尺寸、晶体结构和化学计量的影响。在1773 K的还原气氛下,对250 ~ 3000 ppmw不同浓度的压坯进行了烧结。利用电感耦合等离子体-光学发射光谱、粉末x射线衍射(pXRD)、拉曼光谱、扫描电子显微镜-背散射电子能谱、能量色散能谱和热重分析来评估标记剂在燃料制造过程中的持久性及其对晶粒尺寸、晶格和第一邻化学的影响。我们观察到在烧结过程中铁的损失可以忽略不计。结果表明,在烧结试验条件下,原料Fe2O3转化为Fe和FeO。在所有成分中,金属铁析出相作为次级相存在于晶界中。用pXRD和拉曼光谱测定了离子Fe在UO2单元电池中的潜在掺入。
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Investigation of UO2 doped with Fe2O3 sintered under a reducing atmosphere
Nuclear fuel produced with trace amounts of transition metal additives is of potential interest for introducing intentional signatures for accelerating nuclear forensics. In this work, we investigate the effects on microstructure, grain size, crystal structure, and stoichiometry when trace amounts of Fe in the form of Fe2O3 are added to UO2. Sintering of compacts with different concentrations, from 250 to 3000 ppmw, was performed under a reducing atmosphere at 1773 K. The persistence of the taggant during the fuel fabrication process as well as its impact on grain size, crystal lattice, and first-neighbor chemistry was evaluated using inductively coupled plasma–optical emission spectroscopy, powder X-ray diffraction (pXRD), Raman spectroscopy, scanning electron microscopy–backscatter electron spectroscopy, energy dispersive spectroscopy, and thermogravimetric analysis. We observed that a negligible amount of Fe was lost during sintering. Our results indicate that the feedstock, Fe2O3 transforms into Fe and FeO under the test sintering conditions. For all compositions, metallic Fe precipitate was found in grain boundaries as a secondary phase. The potential incorporation of ionic Fe into the UO2 unit cell was determined by pXRD and Raman spectra.
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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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