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  • Author or Editor: R. Rastogi x
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Abstract  

Extraction of U(IV) by an organic phase containing 30% tri-n-butyl phosphate (TBP) in dodecane from aqueous nitric acid solution containing large amount of U(VI), relevant to nuclear fuel reprocessing by PUREX process, was studied. While acquiring distribution data, an argon atmosphere was maintained. A potentiometric method was used for the determination of U(IV) in the two phases after equilibration. Hydrazine used as stabiliser of U(IV) in the stock solution was destroyed and sulphamic acid was added just before equilibration to avoid the interference due to hydrazine in the subsequent determination of U(IV). Uranium(IV) distribution data between 30% TBP in dodecane and aqueous solution of uranium(VI) and nitric acid of varying concentrations have been presented and compared with available literature data.

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Abstract  

A method based on the back-extraction of Th(IV) from its TTA complex in benzene by aqueous F followed by spectrophotometric measurement of Th(IV), for the determination of fluoride has been developed. The coefficients of variation obtained are 2.4% and 1.4% in 11 determinations at F concentration levels of 1.0 g ml–1, respectively.

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Abstract  

A procedure has been developed for quantitative separation of yttrium from uranium by anion exchange from nearly saturated NH4Cl solution in 0–2N HCl medium. Apparently no organic matter is leached out during the separation as yttrium could be determined by EDTA titration without resorting to fuming with perchloric acid before titration. The precision obtained in the analysis of yttrium in a mixture containing about 12 mg of yttrium and about 300 mg of uranium was ±0.3% (27 determinations).

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Abstract  

Use of hydrogen peroxide as a masking agent for uranium during the EDTA titration of yttrium in an yttrium-uranium mixture containing large amounts of uranium has been investigated. High acetate ion concentration was necessary to keep the peroxy complex of uranium in solution during the titration. It has been observed that upto 500 mg of uranium could be tolerated in the determination of yttrium with 0.5 ml of 30% hydrogen peroxide in {lM acetate medium. The precision and accuracy of the method based on 16 determinations of yttrium at 6–16 mg level in presence of 300 mg uranium has been found to be ±0.2%.

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Abstract  

Determination of fluoride at trace level is important for the specification analysis of nuclear fuel samples. This is generally accomplished by pyrohydrolytic separation followed by ion selective electrode potentiometry. In the present work, a method has been developed for the determination of fluoride by radiometric assay of181Hf back-extracted from thenoyltrifluoracetone (HTTA) in benzene.181Hf back-extracted is proportional to the concentration of fluoride.

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Abstract  

A quartz pyrohydrolysis apparatus designed for the safe handling of pyrophoric carbide nuclear fuel samples while separating C1 and F trace impurities for quality control analysis is described. It has several advantages over the commonly used pyrohydrolysis apparatus. Performance of the apparatus during routine analysis of a large number of nuclear fuel samples has been found to be quite satisfactory.

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