2013
DOI: 10.4236/ijamsc.2013.11008
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Separation Behavior of U(VI) and Th(IV) on a Mixed Ion Exchange Column Using 2,6-Pyridine Dicarboxylic Acid as a Complexing Agent and Determination of Trace Level Thorium in Uranium Matrix Employing High Performance Ion Chromatography

Abstract: Retention behavior of U(VI) and Th(IV) as their 2,6-pyridine dicarboxylic acid (PDCA) complexes on reversed phase and ion exchange (cation, anion and mixed ion exchange) columns was studied and based on the results, a simple ion chromatography method for the determination of trace level thorium in uranium oxide using 0.075 mM 2,6-pyridine dicarboxylic acid (PDCA) and 1 M KNO 3 in 1.2 M HNO 3 as eluent (flow rate 1 mL/min) was proposed. The advantage of the developed method is that the separation of uranium mat… Show more

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Cited by 3 publications
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“… 42 Similar studies were also conducted by Raut et al , which were based on both ion exchange and reverse phase behavior of 2,6-pyridine dicarboxylic acid for the complexation of UO 2 2+ and Th 4+ . 43 In addition, Datta et al have conducted extensive studies on the chromatographic separation of UO 2 2+ and Th 4+ using short columns with small particle sizes to separate UO 2 2+ from Pu 3+ and Pu 4+ . 44 Inspired by the results obtained, they have used monolithic supports modified with bis-2-ethylhexyl succinamic acid as a stationary phase for burn-up measurements of fast reactor fuels.…”
Section: Introductionmentioning
confidence: 99%
“… 42 Similar studies were also conducted by Raut et al , which were based on both ion exchange and reverse phase behavior of 2,6-pyridine dicarboxylic acid for the complexation of UO 2 2+ and Th 4+ . 43 In addition, Datta et al have conducted extensive studies on the chromatographic separation of UO 2 2+ and Th 4+ using short columns with small particle sizes to separate UO 2 2+ from Pu 3+ and Pu 4+ . 44 Inspired by the results obtained, they have used monolithic supports modified with bis-2-ethylhexyl succinamic acid as a stationary phase for burn-up measurements of fast reactor fuels.…”
Section: Introductionmentioning
confidence: 99%