2011
DOI: 10.1007/s10967-011-1460-9
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Removal of Cs from simulated high-level waste solutions by extraction using chlorinated cobaltdicarbollide in a mixture of nitrobenzene and xylene

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Cited by 11 publications
(4 citation statements)
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“…Presence of bulk concentration of Na + in the nuclear waste solution is the major challenge in recovery/removal of Cs + . Literature reports on separation of Cs from nuclear waste solutions include the use of number of techniques viz., precipitation with sodium phosphotungstic acid, ion exchange with silicotitanates, phosphomolybdates and solvent extraction using different macrocyclic ionophores, , protonated form of the hexachlorinated derivative of cobalt bis (dicarbollide) (HCCD). The selective adsorption/extraction of Cs + over Na + using polyphenol enriched biomass based adsorbents or some macrocyclic carrier based solvent extraction methods has also been studied. In order to achieve quantitative separation of Cs from nuclear waste solution, though, several solvents (nitrobenzene, FS-13) and macrocyclic ionophores (bis­(octyloxy) calix[4]­arene-monocrown-6, calix[4]-bis-2,3-naptho-crown-6) , have been synthesized, but high cost of their synthesis and purification necessitates the need for exploring the methods which requires low ligand inventory. Other major disadvantage associated with the conventional separation methods (solvent extraction, ion exchange) is the generation of large amount of secondary waste.…”
Section: Introductionmentioning
confidence: 99%
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“…Presence of bulk concentration of Na + in the nuclear waste solution is the major challenge in recovery/removal of Cs + . Literature reports on separation of Cs from nuclear waste solutions include the use of number of techniques viz., precipitation with sodium phosphotungstic acid, ion exchange with silicotitanates, phosphomolybdates and solvent extraction using different macrocyclic ionophores, , protonated form of the hexachlorinated derivative of cobalt bis (dicarbollide) (HCCD). The selective adsorption/extraction of Cs + over Na + using polyphenol enriched biomass based adsorbents or some macrocyclic carrier based solvent extraction methods has also been studied. In order to achieve quantitative separation of Cs from nuclear waste solution, though, several solvents (nitrobenzene, FS-13) and macrocyclic ionophores (bis­(octyloxy) calix[4]­arene-monocrown-6, calix[4]-bis-2,3-naptho-crown-6) , have been synthesized, but high cost of their synthesis and purification necessitates the need for exploring the methods which requires low ligand inventory. Other major disadvantage associated with the conventional separation methods (solvent extraction, ion exchange) is the generation of large amount of secondary waste.…”
Section: Introductionmentioning
confidence: 99%
“…It is also reported to display good stability toward radiation. 10 The solvent extraction of Cs + using protonated form of CCD − (HCCD) as extractant and trifluoromethylphenyl sulfone (FS-13) 12,14 or nitrobenzene 13 as the solvent is well reported in literature. Selective transport of cesium using HCCD in SLM have been reported with a decontamination factor (DF, defined as the ratio of product to impurity in the receiver divided by that in the feed) of ∼300 over different transition metal ions.…”
Section: ■ Introductionmentioning
confidence: 99%
“…Several methods have been used to enrich and separate low-concentration Cs + from the aqueous solutions. Among these methods, ion-exchange by resins and solvent extraction were considered as the most useful methods and had been extensively studied by many researchers [4][5][6]. The substituted phenols, such as 4-sec-butyl-2(α-methylbenzyl) phenol (BAMBP) and 4-tert-butyl-2 (α-methylbenzyl) phenol (t-BAMBP), are often used as the extractants for Cs + due to high selectivities and easy stripping [3,[7][8][9].…”
Section: Introductionmentioning
confidence: 99%
“…It is known that Cs-137 has properties of high energy gamma ray emission (661.9 keV), heat output (0.42 W/g), and relatively long half-life ( t 1/2 = 30.1 years), and poses threat to final geological disposal. Cs-135 has an extremely long half-life ( t 1/2 = 2.3·10 6 years) and is also an important contributor to the long-term radiological impact on the deep geological repository. , Therefore, separation of radio cesium from HLW will resolve the radiation exposure problem during radioactive waste handling and can also reduce the risk to the vitrified waste storage. Moreover, the separated Cs-137 can be utilized as resources of β-radiation and energy generators in industrial determination and hospital examination.…”
Section: Introductionmentioning
confidence: 99%