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INVESTIGATION OF URANIUM IN BIS(TRIFLUOROMETHYLSULFONYL)IMIDE BASED IONIC LIQUIDS

机译:双(三氟甲基磺酰)亚胺基离子液体中铀的研究

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摘要

The development of industrial scale ionic liquid based flow sheets is the anticipated outgrowth of fundamental ionic liquid research. The Nuclear Materials Technology (NMT) and Engineering Sciences and Applications (ESA) Divisions at Los Alamos National Laboratory are continuing the development of advanced uranium Decontamination and Conversion (D&C) systems based on the electrolytic stripping of plutonium contaminated uranium surfaces. Development of the aqueous D&C flow sheet has presented several challenges. Chief among these is the need to mitigate the safety concerns associated with the generation of hydrogen during electrolysis. We have found that the effectiveness of the stripping process is in some cases limited by film formation on the uranium anode. The aqueous flow sheet is further complicated by the requirement for pH control throughout the run, and by the ill-defined plutonium baring hydrolysis residues. Our presentation will focus on the preliminary development work toward an ionic liquid based alternative to the current aqueous process.
机译:工业规模的基于离子液体的流程图的发展是基础离子液体研究的预期结果。洛斯阿拉莫斯国家实验室的核材料技术(NMT)部门和工程科学与应用(ESA)部门正在继续开发基于电解法去除受minated污染的铀表面的先进铀去污和转化(D&C)系统。水性D&C流程表的开发提出了一些挑战。其中最主要的是需要减轻与电解过程中产生氢气有关的安全问题。我们发现,在某些情况下,汽提过程的有效性受到铀阳极上成膜的限制。由于在整个运行过程中都需要控制pH值,以及flow定义不明确的水解残渣,使得水性流程更加复杂。我们的演讲将集中于针对目前水性工艺的基于离子液体的替代品的初步开发工作。

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