首页> 外文期刊>Radiochimica Acta: International Journal for Chemical Aspects of Nuclear Science and Technology >Solvent extraction of uranium(VI) by a dipicolinamide using a room-temperature ionic liquid
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Solvent extraction of uranium(VI) by a dipicolinamide using a room-temperature ionic liquid

机译:使用室温离子液体通过二吡啶甲酰胺溶剂萃取铀(VI)

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摘要

Room-temperature ionic liquids (RTILs) have recently received increasing attention as solvent alternatives for possible application in spent fuel reprocessing, particularly in the extraction of metal ions from high-level radioactive aqueous waste, due to their unique physical and chemical properties. Herein, the solvent extraction of the uranyl ions (UO_2~(2+)) was performed using N,N'-diethyl-N,N'-di(para)tolyl-dipicolinamide (Et_((p))TDPA) as the extractant in a commonly used ionic liquid 1-butyl-3- methylimidazolium hexafluorophosphate ([C_4mim][PF_6]). The effects of vortexing time, phase ratio and the concentration dependence of Et_((p))TDPA, nitric acid and sodium nitrate on the extraction were studied in detail. The extraction mechanism was deduced based on the slope analysis and UV-vis measurement. The distribution ratio of U from 3 mol/Lnitricacid by 0.3 mol/LEtTDPA/C_4mimPF_6 is found to be almost 100. Conventional log-log plot analysis of the extraction equilibrium data suggests that the ions are extracted as a complex in 2: 3 ratio of UO_2~(2+) to extractant, and the extractionmost likely occurs by a cationexchange mode since the concentration of C_4mim~+ in the aqueous phase increases linearly with the percent extraction of UO_2~(2+) evidenced by UV-vis measurement. This work promises to provide new efficient media based on RTILs for separation of uraniumfromthe radioactive aqueous waste.
机译:室温离子液体(RTILs)由于其独特的物理和化学特性,作为溶剂替代品的可能替代品,近年来越来越受到关注,因为它们可能用于乏燃料后处理,特别是从高放射性放射性废水中提取金属离​​子。在此,使用N,N'-二乙基-N,N'-二(对)甲苯基-二吡啶甲酰胺(Et _((p))TDPA)作为溶剂进行铀酰离子(UO_2〜(2+))的溶剂萃取。常用离子液体1-丁基-3-甲基咪唑鎓六氟磷酸盐([C_4mim] [PF_6])中的萃取剂。详细研究了涡旋时间,相比和Et _((p))TDPA,硝酸和硝酸钠的浓度依赖性对提取的影响。根据斜率分析和紫外可见测量推导了萃取机理。从3摩尔/硝酸到0.3摩尔/ LEtTDPA / C_4mimPF_6的U分布比几乎为100。提取平衡数据的常规对数-对数图分析表明,离子以2:3的比例作为复合物提取。 UO_2〜(2+)萃取到萃取剂中,萃取最有可能通过阳离子交换模式发生,因为水相中C_4mim〜+的浓度与UV-vis测量所证明的UO_2〜(2+)萃取百分比呈线性关系。这项工作有望提供一种基于RTIL的新型高效介质,用于从放射性含水废物中分离铀。

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