The extraction of SR2+ with dicyclohexano-18-crown-6 in conventional organic solvent and ionic liquid diluents

Abstract

90 Sr (t 1/2 = 28.8 a), one of the most significant fission products in high-level radioactive liquid waste (HLLW), contributes to a large part of the heat load and radiation. Removal of 90 Sr from the HLLW is beneficial for the final treatment of nuclear waste. In this paper, the extraction of Sr 2+ was carried out using dicyclohexano-18-crown-6 (DCH18C6) in a variety of diluents including conventional organic solvents and novel ionic liquid solvents. The effect of several factors, such as nitric acid concentration, crown ether concentration and initial strontium concentration on the extraction of Sr 2+ have been studied comprehensively. The higher distribution ratio and the stripping efficiency of Sr 2+ were obtained with the binary diluents consisted of n-octanol and acetylene tetrachloride, which were compared with that using pure n-octanol as diluent. As for the C n mimNTf 2 (n = 2, 4, 6) ionic liquid solvent systems, the distribution ratio of Sr 2+ was much higher in the nitric acid medium with low concentration than in the traditional solvent systems. The results showed that D C2mimNTf2 > D C4mimNTf2 > D C6mimNTf2 , which indicated that shorter carbon chain benefits the extraction of Sr 2+ .

Chelating Extractants for Metals

“…However, the extraction efficiency of the perrenate ions was practically independent of the uranium concentration when the nitric acid concentration was approximately 3 However, a common disadvantage of the works [80][81][82] is the lack of data on the influence of other radionuclide impurities on 90 Sr extraction.…”

“…The extraction of Sr (II) from nitric acid media using dicyclohexano-18-crown-6 ether 62 dissolved both in common organic solvents and in ionic liquids 3, 63, 64 was studied [82]. The dependence of Sr (II) extraction degree on concentrations of nitric acid, crown ether and initial concentration of strontium was determined.…”

“…However, a common disadvantage of the works [80][81][82] is the lack of data on the influence of other radionuclide impurities on 90 Sr extraction.…”

High strontium adsorption performance of layered zirconium phosphate intercalated with a crown ether

“…7,35–38 However, as an organic material, post-treatment of the crown ether after nuclear waste adsorption poses a challenge. 38…”

“…19,34 As a result, the 18C6 has become the most studied extractant in the removal of Sr-90 from highly radioactive waste streams. 7,[35][36][37][38] However, as an organic material, posttreatment of the crown ether aer nuclear waste adsorption poses a challenge. 38 In this experiment, the target products were synthesized by a pre-intercalation method.…”