Investigating the interactions between hydrotalcite and U(IV) nanoparticulates

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Chris Foster , Samuel Shaw , Thomas S. Neill , Nick Bryan , Nick Sherriff , Scott Harrison , Louise S. Natrajan , Bruce Rigby , Katherine Morris
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引用次数: 0

Abstract

In the UK, the decommissioning of legacy spent fuel storage facilities at the Sellafield nuclear facility requires the retrieval of radioactive sludge resulting from Magnox fuel corrosion. However, sludge retrievals may enhance uranium mobility including via sorption of radionuclide nanoparticles onto colloidal phases such as hydrotalcite (Mg4Al2(OH)16(CO3).4H2O). Hydrotalcite is a Mg-Al layered double hydroxide (LDH) which is a corrosion product of Magnox fuel cladding. Currently, there are a paucity of studies examining interactions between actinide nanoparticles and LDH phases such as hydrotalcite. Here, a multi-technique approach was used to investigate the interactions between colloidal hydrotalcite and three different forms of nanoparticulate U(IV): nanoparticulate uraninite (UO2); nanoparticulate UO2 reacted with silica (UO2-Si); and U(IV)-Si-coprecipitate under anoxic, neutral-to-alkaline conditions. Ultrafiltration and zeta potential analyses indicated that for UO2 and UO2-Si nanoparticulate phases, sorption to colloidal hydrotalcite was limited due to rapidly settling UO2 and UO2-Si aggregates (>450 nm). By contrast, ultrafiltration and zeta potential analyses confirmed the U(IV)-Si-coprecipitate nanoparticle phase showed significantly higher sorption to colloidal hydrotalcite. This was due to the increased colloidal stability of intrinsic U(IV)-silicate nanoparticles which in turn promoted increased sorption to hydrotalcite. TEM imaging showed some evidence for smaller UO2 and UO2-Si aggregates (<20 nm) sorbed to colloidal hydrotalcite. Similar behaviour was observed in TEM images of authentic pond effluent samples from Sellafield, providing confidence that the model laboratory experiments provided a bridge to the highly radioactive spent nuclear fuel pond interactions. This study highlights the potential for U(IV) nanoparticles to form a new type of colloid-colloid interaction with hydrotalcite, especially when silica is present. This further informs predictions of U(IV) (and An(IV)) behaviour in the legacy pond and silo environments, as well as in environmental scenarios where LDH mineral phases and silica are present (e.g. in geological disposal of radioactive waste).

研究水滑石与U(IV)纳米颗粒之间的相互作用
在英国,塞拉菲尔德核设施的废弃乏燃料储存设施需要回收由镁诺克斯燃料腐蚀产生的放射性污泥。然而,污泥回收可以提高铀的流动性,包括通过将放射性核素纳米颗粒吸附到胶体相上,如水滑石(Mg4Al2(OH)16(CO3). 4h2o)。水滑石是镁铝层状双氢氧化物(LDH),是镁氧化物燃料包壳的腐蚀产物。目前,研究锕系纳米粒子与LDH相(如水滑石)之间相互作用的研究很少。本文采用多技术方法研究了胶体水滑石与三种不同形式的纳米颗粒铀(IV)之间的相互作用:纳米颗粒铀矿(UO2);纳米UO2与二氧化硅反应(UO2- si);和U(IV)- si在缺氧、中碱性条件下共沉淀。超滤和zeta电位分析表明,对于UO2和UO2- si纳米颗粒相,由于UO2和UO2- si团聚体(>450 nm)的快速沉降,胶体水滑石的吸附受到限制。相比之下,超滤和zeta电位分析证实了U(IV)- si共沉淀纳米颗粒相对胶体水滑石的吸附性显著提高。这是由于固有的U(IV)-硅酸盐纳米颗粒的胶体稳定性增加,这反过来又促进了水滑石的吸附增加。TEM成像显示有一些证据表明,胶体水滑石上吸附了较小的UO2和UO2- si聚集体(< 20nm)。在塞拉菲尔德的真实池塘流出物样本的TEM图像中也观察到了类似的行为,这为模型实验室实验为高放射性乏核燃料池相互作用提供了一个桥梁提供了信心。这项研究强调了U(IV)纳米颗粒与水滑石形成新型胶体-胶体相互作用的潜力,特别是当二氧化硅存在时。这进一步有助于预测U(IV)(和An(IV))在遗留池塘和筒仓环境中的行为,以及在LDH矿物相和二氧化硅存在的环境情景中(例如在放射性废物的地质处置中)。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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