UO2 在熔融 LiCl-Li2O 中的溶解度和化学相互作用

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-06-05 DOI:10.1016/j.jnucmat.2024.155220
Mario Alberto Gonzalez , Cameron Leavitt , Justin M. Holland , Michael F. Simpson
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引用次数: 0

摘要

本研究调查了二氧化铀在 650 °C、氧气分压高达 114 托的条件下在 LiCl-2 wt% Li2O 中的溶解度。实验中,二氧化铀粉末与熔盐接触长达 120 小时。盐样品被采集并使用电感耦合等离子体质谱法分析铀和腐蚀产物的浓度,使用滴定法分析 Li2O 的浓度。测得的盐中最高铀浓度为 0.06 wt%,观察到氧气分压对溶解度几乎没有影响。增加氧气分压确实会增加盐中腐蚀产物的浓度。熔盐中的 Li2O 浓度随着与二氧化铀接触时间的延长而逐渐降低。这可以用二氧化硫与 Li2O 反应生成 Li2UO4 来解释。
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UO2 solubility and chemical interactions in molten LiCl-Li2O

This study investigated the solubility of UO2 in LiCl-2 wt% Li2O at 650 °C with O2 partial pressures up to 114 torr. Experiments were run in which UO2 powder was contacted with the molten salt for up to 120 h. Salt samples were taken and analyzed for U and corrosion product concentration using inductively coupled plasma mass spectrometry and for Li2O concentration using titration. The highest measured U concentration in the salt was 0.06 wt%, and O2 partial pressure was observed to have little to no effect on the solubility. Increasing O2 partial pressure did increase the concentration of corrosion products in the salt. The concentration of Li2O in the molten salt progressively decreased with time in contact with UO2. This can be explained by the formation of Li2UO4 via reaction of UO2 with Li2O.

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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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