摘要
比较研究了混合三烷基氧膦 ( TRPO) -磷酸三丁酯 ( TBP) /煤油混合体系和 TRPO/煤油体系对铀和硝酸的萃取容量 ,结果表明 ,混合体系的萃取容量比 TRPO/煤油体系高。测定了 2 0 % TRPO- 2 0 %TBP/煤油混合体系对二十余种离子的萃取分配比 ,结果表明在较宽的 HNO3浓度范围 ( 0 .5～ 5mol/L)内 ,该混合体系对低浓度 UO2 2 +、低浓度 U4 +、Pu4 +、Pu3+、Np O2 2 +、Np4 +都有较高的萃取能力 ;低酸条件( <1.0 mol/L)下 ,混合体系对 Tc O4 -、Am3+、Eu3+、Y3+有较高的分配比 ;混合体系对 Np O2 +、Sr2 +、Cs+等的萃取能力较弱。TRPO- TBP/煤油有机相中萃取的镅、铀、钚和锝可以分别用高浓度硝酸、碳酸铵溶液、羟基乙酸和高浓度硝酸 (或碳酸盐 )反萃下来。
The extraction capacity of uranium and nitric acid in both TRPO mixed trialkyl phosphine oxide TBP tributyl phosphate/kerosene system and TRPO/kerosene system are compared. The results demonstrated that TRPO TBP/kerosene system have higher extraction capacity for uranium and nitric acid than TRPO/kerosene system. The distribution ratios of more than 20 ions with 20%TRPO 20%TBP/kerosene system were measured. The experiments showed that the extractant have high extraction ability for low concentration UO 2 2+ , low concentration U 4+ , Pu 4+ , Pu 3+ , NpO 2 2+ and Np 4+ etc in broad range of nitric acid concentration 0.5~5 mol/L. It was also known that the system have high distribution ratios for TcO 4 -, Am 3+ , Eu 3+ and Y 3+ etc in low concentration of nitric acid less than 1.0 mol/L but hardly extract NpO 2 +、Sr 2+ and Cs + etc. The americium, uranium, plutonium and technetium can be back extracted efficiently from this organic phase by high concentration of nitric acid higher than 5.0 mol/L, ammonium carbonate, hydroxy acetic acid, and high concentration of nitric acid or ammonium carbonate respectively.
出处
《辐射防护》
CAS
CSCD
北大核心
2001年第2期93-97,共5页
Radiation Protection
关键词
TRPO
TBP
煤油
萃取
反萃
高放废液处理
萃取容量
放射性核素
镅
铀
钚
锝
TRPO mixed trialkyl phosphine oxide TBP tributyl phosphate/kerosene
extraction
back extraction
extraction capacity
