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Recovery of uranium from residue generated during Mo-99 production, using organic solvent extraction
Physics and Chemistry of the Earth, Parts A/B/C ( IF 3.0 ) Pub Date : 2019-11-22 , DOI: 10.1016/j.pce.2019.102822
Naomi D. Mokhine , Manny Mathuthu , Elizabeth Stassen

During the production of the medical isotope Mo-99, the uranium and some fission products are precipitated as residue of mixed hydrated oxides. However, the PUREX extraction of uranium, plutonium is extracted, raising proliferation issues. The aim of this research was to characterize the most effective organic solvent for the recovery of uranium. Uranium oxide was dissolved in ammonium carbonate solution to form uranium tri-carbonate aqueous feed solution. Results show that 0.2 M ammonium carbonate and 0.01 M uranium mixed with 15% Aliquat 336 in Toluene at volume ratio (A/O) of 1:5 produced 98% extraction of uranium from the alkaline media.



中文翻译:

使用有机溶剂萃取,从Mo-99生产过程中产生的残留物中回收铀

在医学同位素Mo-99的生产过程中,铀和某些裂变产物会作为混合水合氧化物的残留物沉淀出来。但是,PUREX提取铀时,会提取p,从而引起扩散问题。这项研究的目的是表征最有效的铀回收有机溶剂。将氧化铀溶解在碳酸铵溶液中,以形成三碳酸铀水溶液进料溶液。结果显示,将0.2 M碳酸铵和0.01 M铀与15%Aliquat 336在甲苯中的体积比(A / O)为1:5混合,可以从碱性介质中提取98%的铀。

更新日期:2020-04-12
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