N,N'-四己基丙二酰胺-正辛烷溶液 从硝酸介质中萃取铀  

Extraction of uranium(VI) from nitric acid solutions with N ,N'- tetrahexylmalonamide in n- Octane

作　　者：孙国新[1] 韩景田[1] 包伯荣[1] 崔玉[2] 鲍猛[2] 

机构地区：[1]中国科学院上海原子核研究所,上海201800 [2]山东建材学院,济南250022

出　　处：《核技术》1999年第2期114-118,共5页Nuclear Techniques

摘　　要：研究了新萃取剂Ｎ，Ｎ＇－四己基丙二酰胺－正辛烷溶液从硝酸介质中萃取铀的机理。考察 了水相硝酸浓度、萃取剂浓度、硝酸钠浓度以及温度对萃取分配比的影响，确定了萃合物的组 成。借助红外光谱分析了萃合物的结构。求得了萃取硝酸铀酰的平衡常数及反应的热力学函 数。与四丁基丙二酰胺相比减少了三相生成的倾向。同时研究了稀释剂的影响，发现该萃取剂 在正辛烷中比在甲苯中萃取能力强，并对上述结果进行了解释。The mechanism of extraction of uranium(VI) from nitric acid solutions with anovel extractant N,N'-tetrahexylmalonamide (THMA) in n-octane was investigated. The effects of concentrations of aqueous nitric acid, extractant and sodium nitrate and also the temperature on extraction distribution ratios were studied. The extraction stoichiometry was established and the structure of extracted complex was analyzed by means of the IR spectra.The extraction constant of uranium(VI) with THMA and the reaction enthalpy were calculated.Compared with N,N'-tetrabutyl- malonamide (TBMA),it is shown that the increase of the alkyl chain for THMA lowers the formation of third phase. The study of the effect of diluents indicates that the extractability of THMA in n-octane for uranium(Vl ) is higher than that in toluene.

关 键 词：四己基丙二酰胺 铀 萃取 正辛烷 硝酸介质 

分 类 号：TL241.14[核科学技术—核燃料循环与材料]