A novel biamperometric methodology for thorium determination by EDTA complexometric titration

Jayachandran, Kavitha; Gamare, Jayashree; Nair, P.M.; Xavier, Mary

doi:10.1524/ract.2012.1920

Cited by 11 publications

(1 citation statement)

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“…Concentrations of U, Pu and Nd in the sample were found to be 5.3 ± 0.3 % g/g, 26.8 ± 0.2% g/g and 1.8 ± 0.2% g/g, respectively. Concentration of Th in the dissolver solution, determined biampero metrically using EDTA as a titrant, was found to be 1.03 ± 0.2% mg/g [30]. The concentrations of Nd, Th, U and Pu obtained were in good agreement with the concentrations determined by HPLC.…”

Section: Mechanism Of Retention Of Th U and Pusupporting

confidence: 69%

Determination of Lanthanides, Thorium, Uranium and Plutonium in Irradiated (Th, Pu)O2 by Liquid Chromatography Using α-Hydroxyiso Butyric Acid (α-HIBA)

Kumar¹,

Jaison²,

Telmore³

et al. 2013

IJAMSC

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An HPLC method is presented for the separation and determination of lanthanides (Lns), thorium (Th), uranium (U) and plutonium (Pu) from irradiated (Th, Pu)O 2 . Individual separation of Lns, Th, U and Pu is a challenging task because of 1) lanthanides having similar physical and chemical properties, 2) presence of complex matrix like irradiated fuel and 3) the co-existence of multiple oxidation states of Pu. Different procedures were developed for separation of individual lanthanides and actinides. The individual lanthanides were separated on a dynamically modified reversed phase (RP) column using n-octane sulfonic acid as an ion interaction reagent and employing dual gradient (pH and concentration) of α-hydroxyisobutyric acid (HIBA). In order to improve the precision on the determination of Lns, terbium (Tb) was used as an internal standard. The method was validated employing simulated high level liquid waste. Concentrations of lanthanides viz. lanthanum (La) and neodymium (Nd) in the dissolver solution were determined based on their peak areas. Th, U and Pu were separated on a RP column using mobile phase containing HIBA and methanol. Since Pu is prone to exist in multiple oxidation states, all the oxidation states were converted into Pu (IV) using H 2 O 2 in 3 M HNO 3 . Under the optimized conditions, Pu(IV) eluted first followed by Th and U. The concentrations of Th, U and Pu were determined by standard addition method and were found to be 1.10 ± 0.02 mg/g, 5.3 ± 0.3 µg/g and 27 ± 1 µg/g, respectively, in the dissolver solution of irradiated fuel. These values were in good agreement with the concentration of Th determined by biamperometry and those of U and Pu by isotope dilution thermal ionization mass spectrometry.

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Section: Mechanism Of Retention Of Th U and Pusupporting

confidence: 69%