Sorption of 85Sr, 137Cs, and 152Eu from solutions on mixed hexacyanoferrates of potassium and uranyl

Kulyukhin, S. A.; Krasavina, E. P.; Gorbacheva, M. P.; Rumer, I. A.; Konovalova, N. A.; Mizina, L. V.; Tanashchuk, N. V.

doi:10.1134/s1066362207010134

Cited by 2 publications

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“…The results obtained showed that the degree of 137 Cs and 85 Sr sorption recovery from aqueous solutions upon their 120 min contact with AE hydroxyphosphate is ∼ 5-25% and ∼ 15-80%, respectively. The sorption of 85 Sr, 137 Cs and 152 Eu from solutions on mixed hexacyanoferrates of potassium and uranyl was studied by Kulyukhin et al [12]. The distribution coefficients of 85 Sr, 137 Cs and 152 Eu are determined to be 210, 3000 and 1100 ml/g, respectively.…”

Section: Introductionmentioning

confidence: 99%

Improvement of radioactive liquid waste treatment efficiency by sequential cationic and anionic ion exchangers

Borai¹,

Hilal²,

Attallah³

et al. 2008

Radiochimica Acta

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Liquid radioactive / Waste treatment / Ion exchange / Radionuclides / Complexant / Cesium removalSummary. Various types of liquid radioactive wastes are released from different nuclear activities. The treatment efficiencies of these wastes depend highly on the physical and chemical composition of each waste such as pH, TDS and electrical conductivity. The treatment efficiency of some radionuclides with different valency states (such as 134 Cs, 65 Zn, 60 Co and 152+154 Eu) was tested based on the absorption capacity of cationic exchanger (KY-2) functionlized with polystyrene sulphonic group. The competitive adsorption on cationic exchanger was investigated by mono radionuclide and multi radionuclides wastes. The influence of the presence of various anionic complexants in the rad-waste on the adsorption capacity and hence the treatment efficiency was quantitatively studied using weakly base aminated anionic exchanger (AN-31). The enhancement in decontamination factor of each radionuclide is mostly attributed to the high adsorption capacity of the cationic resin in addition to the complexation capability of the radionuclide with the different complexant existed in the waste solution. The complex formation improved the decontamination factor through indirect adsorption of the anionic species on the subsequent anionic exchanger during the treatment process. The results showed that the removal percentages are around 50% for 134 Cs, 60 Co, 65 Zn and 152,154 Eu, without complexant compound. Significant enhancements of the removal percentages > 85% were obtained for 60 Co, 65 Zn and 152,154 Eu, respectively, on addition of manganese sulphate while maximum removal percentage (75.3 ± 0.7%) is obtained for 134 Cs when using 0.1 M citric acid as a complexing agent.

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Section: Introductionmentioning

confidence: 99%