No abstract

The separation of Li+ from an aqueous solution has received much attention in recent years because of its wide application in batteries and nuclear energy. A cellulose microsphere adsorbent with sulfonic acid groups (named as CGS) was successfully prepared by the pre-irradiation-induced emulsion graft polymerization of glycidyl methacrylate onto cellulose microspheres through subsequent sulfonation and protonation. The adsorption performance of Li+ onto the CGS adsorbent is investigated in detail. The as-prepared CGS adsorbent exhibited fast adsorption kinetics and a high adsorption capacity of Li+ (16.0 mg/g) in a wide pH range from 4 to 10. The existence of K+ and Na+ was found to have the ability to affect the adsorption capacity of Li+ due to the cation-exchange adsorption mechanism, which was further confirmed by X-ray photoelectron spectroscopy (XPS). The column adsorption experiment indicated that the adsorption capacity of CGS agreed well with the batch adsorption, and a fast desorption could be obtained in 10 min. It is expected that CGS has potential usage in the adsorption separation of Li+ from an aqueous solution.

The quantitative analysis and identification of the radiolytic products of dicyclohexano-18-crown-6 (DCH18C6), 4',4''(5'')-di-tert-butyldicyclohexano-18-crown-6 (DtBuCH18C6) and benzo-18-crown-6 (B18C6) in 1-butyl-3-methylimidazolium bis(trifluoromethylsulfonyl) imide ([C4mim][NTf2]) ionic liquid after irradiation were performed for the first time. It was found that the yield for radiolytic destruction of DCH18C6 and DtBuCH18C6 was less than that for B18C6. The main radiolytic products were identified as substituted crown ethers formed between crown ether and active radicals such as methyl, trifluoromethyl, butyl, and [C4mim]˙ radicals generated during the irradiation of the crown ether-[C4mim][NTf2] system. The radiation effect on the Sr(2+) partitioning of the crown ether-[C4mim][NTf2] system shows further that DCH18C6-[C4mim][NTf2] and DtBuCH18C6-[C4mim][NTf2] still have good extractability for Sr(2+) after irradiation. The extraction ability of DCH18C6-[C4mim][NTf2] and DtBuCH18C6-[C4mim][NTf2] system for Sr(2+) decreased by 14.4% and 18.2% even at 500 kGy, respectively.