摘要
研究了酰胺荚醚N ,N ,N′,N′ 四丁基 3 氧 戊二酰胺 (TBOPDA)和N 50 3(N ,N′ 二乙基庚酰胺 )以及TBOPDA与N 50 3的组合萃取剂在硝酸介质中对U (Ⅵ )、Pu(Ⅳ )、Am(Ⅲ )、Eu(Ⅲ )和其他一些金属离子的萃取行为 ,稀释剂为 4 0 %正辛醇 煤油。用 0 0 75mol/LTBOPDA +0 5mol/LN 50 3/ 4 0 %辛醇 煤油为萃取剂 ,从模拟高放废液中分离U(Ⅵ )、Pu(Ⅳ )、Am(Ⅲ )和Eu(Ⅲ )的微型混合澄清槽实验结果表明 :在A槽 ,大于 99 99%的U(Ⅵ )、Pu(Ⅳ )、Eu(Ⅲ )和Am(Ⅲ )被萃入有机相 ;在R1槽 ,U(Ⅵ )被定量反萃 ,83 %的Pu(Ⅳ )和 36%的Am(Ⅲ )被反萃入水相 ;在R2槽中残留的Pu(Ⅳ )、Am(Ⅲ )和Eu(Ⅲ )可被定量反萃下来。该流程可有效提取高放废液中的锕系元素 ,并可对其进行组分离。
The extraction behaviour of U(Ⅵ),Pu(Ⅳ),Am(Ⅲ),Eu(Ⅲ) and some other cations is investigated using amido podands, such as TBOPDA(N,N,N′N′ tetrabutyl 3 oxy pentandiamide) or a mixture of TBOPDA and N 503 (N, N′ diethylheptamide) as extractants, and 40 % octanol and kerosene as diluent for both cases. On the basis of tuble tests, courtcurrent experiments with miniature mix settler is carried out to separate U(Ⅵ),Pu(Ⅳ),Am(Ⅲ) and Eu(Ⅲ) from simulated high level liquid waste solution by the extractant of 0.075 mol/L TBOPDA+ 0.5 mol/L N 503/40 % octanol kerosene. In the coextraction battery, more than 99.9 % of U(Ⅵ), Pu(Ⅳ) , Eu(Ⅲ) and Am(Ⅲ) is extracted into organic phase. 83 % of Pu(Ⅳ) and 36 % of Am(Ⅲ) are striped into aqueous in first back extraction battery, and in the second one the remaind Pu(Ⅳ),Am(Ⅲ) and Eu(Ⅲ) are striped completely. The results show that this flowsheet is highly effective on recover and group actinides and lanthanides from high level liquid waste.
出处
《原子能科学技术》
EI
CAS
CSCD
2001年第B05期62-69,共8页
Atomic Energy Science and Technology
