Foster Chris, Shaw Samuel, Neill Thomas S, Bryan Nick, Sherriff Nick, Natrajan Louise S, Wilson Hannah, Lopez-Odriozola Laura, Rigby Bruce, Haigh Sarah J, Zou Yi-Chao, Harrison Robert, Morris Katherine
Research Centre for Radwaste Disposal and Williamson Research Centre, Department of Earth & Environmental Sciences, The University of Manchester, Oxford Road, Manchester M13 9PL, U.K.
National Nuclear Laboratory, Chadwick House, Warrington Road, Birchwood Park, Warrington WA3 6AE, U.K.
Langmuir. 2022 Mar 1;38(8):2576-2589. doi: 10.1021/acs.langmuir.1c03179. Epub 2022 Feb 15.
In the United Kingdom, decommissioning of legacy spent fuel storage facilities involves the retrieval of radioactive sludges that have formed as a result of corrosion of Magnox nuclear fuel. Retrieval of sludges may re-suspend a colloidal fraction of the sludge, thereby potentially enhancing the mobility of radionuclides including uranium. The colloidal properties of the layered double hydroxide (LDH) phase hydrotalcite, a key product of Magnox fuel corrosion, and its interactions with U(VI) are of interest. This is because colloidal hydrotalcite is a potential transport vector for U(VI) under the neutral-to-alkaline conditions characteristic of the legacy storage facilities and other nuclear decommissioning scenarios. Here, a multi-technique approach was used to investigate the colloidal stability of hydrotalcite and the U(VI) sorption mechanism(s) across pH 7-11.5 and with variable U(VI) surface loadings (0.01-1 wt %). Overall, hydrotalcite was found to form stable colloidal suspensions between pH 7 and 11.5, with some evidence for Mg leaching from hydrotalcite colloids at pH ≤ 9. For systems with U present, >98% of U(VI) was removed from the solution in the presence of hydrotalcite, regardless of pH and U loading, although the sorption mode was affected by both pH and U concentrations. Under alkaline conditions, U(VI) surface precipitates formed on the colloidal hydrotalcite nanoparticle surface. Under more circumneutral conditions, Mg leaching from hydrotalcite and more facile exchange of interlayer carbonate with the surrounding solution led to the formation of uranyl carbonate species (e.g., Mg(UO(CO))). Both X-ray absorption spectroscopy (XAS) and luminescence analysis confirmed that these negatively charged species sorbed as both outer- and inner-sphere tertiary complexes on the hydrotalcite surface. These results demonstrate that hydrotalcite can form pseudo-colloids with U(VI) under a wide range of pH conditions and have clear implications for understanding the uranium behavior in environments where hydrotalcite and other LDHs may be present.
在英国,遗留乏燃料储存设施的退役涉及回收因镁诺克斯型核燃料腐蚀而形成的放射性污泥。污泥的回收可能会使污泥的胶体部分重新悬浮,从而有可能提高包括铀在内的放射性核素的迁移率。镁诺克斯型燃料腐蚀的关键产物层状双氢氧化物(LDH)相水滑石的胶体性质及其与U(VI)的相互作用备受关注。这是因为在遗留储存设施和其他核退役场景所特有的中性至碱性条件下,胶体水滑石是U(VI)的潜在传输载体。在此,采用了多种技术方法来研究水滑石在pH值7 - 11.5范围内以及不同U(VI)表面负载量(0.01 - 1 wt%)下的胶体稳定性和U(VI)吸附机制。总体而言,发现水滑石在pH值7至11.5之间形成稳定的胶体悬浮液,有证据表明在pH≤9时镁会从水滑石胶体中浸出。对于存在U的体系,无论pH值和U负载量如何,在水滑石存在的情况下,>98%的U(VI)会从溶液中去除,尽管吸附模式受pH值和U浓度的影响。在碱性条件下,U(VI)表面沉淀在胶体水滑石纳米颗粒表面形成。在更接近中性的条件下,镁从水滑石中浸出以及层间碳酸盐与周围溶液更易发生交换,导致形成碳酸铀酰物种(例如,Mg(UO(CO)))。X射线吸收光谱(XAS)和发光分析均证实,这些带负电荷的物种作为外层和内层球三级配合物吸附在水滑石表面。这些结果表明,水滑石在广泛的pH条件下可与U(VI)形成假胶体,对于理解水滑石和其他层状双氢氧化物可能存在的环境中的铀行为具有明确意义。