Electrodeposition Of Uranium Research Articles

Preparation of α-sources of U(VI) and Th(IV) by the electrodeposition technique in the presence of Ca 2+ and some trivalent metals

A new method for the electrodeposition of uranium and thorium from an aqueous/ethanol media in the presence of Ca(II) and some trivalent metals is described. The deposition is carried out at a constant weak voltage of 30 V and starting current intensity of 3A. The deposition yields of uranium is investigated as a function of the amounts of various carriers and impurities such as Fe, Al, Bi, La and Ca as well as acetic, nitric and hydrochloric acids. All solutions containing up to 900 ppm of Ca 2+ and 100 –150 μg of the foreign ions namely: Fe, Bi or La can be used with no chemical separation. Uranium and thorium recoveries between 80 and 96% are obtained and the resolution is typically 25–40 keV. Procedure without chemical purification is proposed for a selective electrodeposition of U(VI) and Th(IV) from one another and from calcium.

On the energy resolution of α-sources prepared by electrodeposition of uranium

Using energy-dispersive X-ray fluorescence (EDXF) analysis of electrodeposited α-sources, we show that, after heating to glowing, the deposited material on the metal plates takes the form of very small spheres. Moreover, the average diameter of these spheres is found to depend on the degree of smoothness of the metal-plate surface. In addition, this spherelike material is found to consist not only of uranium but also of platinum, the latter of which originates from the platinum anode used for electrodeposition. Consequently, the energy resolution of α-sources prepared in this way is dependent not only on the physical attributes of the surface of the planchets used, but also on the duration of deposition.

New developments in target preparation at CBNM: laser evaporation-condensation and electrolysis

Preliminary laser evaporation-condensation experiments were performed to check the quantitative deposition of lithium fluoride and uranium oxide. The homogeneity of the deposits on stainless steel backings was investigated. Interaction of polyimide foils with the laser beam was also observed. Electrodeposition of uranium and plutonium on gold-coated polyimide foils was investigated in aqueous and organic media.

Optimal parameters for the electrodeposition of uranium

Some remarks are given comparing two recently published methods of electrodeposition of uranium on stainless steel planchets to prepare sources for α-spectrometry. Parameters used in the two procedures are discussed, and a general method of determining the best electrodeposition yield is proposed.

Electrodeposition of actinide traces from aqueous alkaline solutions and tributyl phosphate

The electrodeposition of uranium and trace quantities of239Pu,234Th,144Ce on a stainless steel disk has been investigated from 0.5–2.0M NaOH and the two-phase system: extract of actinides in TBP-aqueous solution of NaOH. The electrodeposition yield of the above elements reaches 98–100% in 40 min of electrolysis with current density 0.4–0.5 A/cm2. The presence of 0.5M Na2CO3, 2.0M NaNO3, 2.0M NaNO2, 0.2M NaF in alkaline solutions does not decrease the electrodeposition yield. The electrodeposited films meet all the requirements of α-spectrometry. The uranium oxidation states (V) and (IV) have been determined in the electrodeposited films.

Studies on electrodeposition of actinide elements from non-aqueous medium

Electrodeposition of uranium, neptunium and thorium from isopropyl alcohol medium was studied in some detail with a view to understanding the mechanism of electrodeposition of actinides from organic medium. The deposits obtained by the electrodeposition of uranium, thorium and neptunium were examined by various techniques. The presence of hydroxyl-rich layer at the cathode was detected using phenolphathaline indicator. From the data gathered in this investigation it was concluded that these actinides are deposited as hydrolytic species from an organic medium as they are from an aqueous medium.

Electrodeposition of Uranium from Urine

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Electrodeposition of Uranium at the Microgram Level

The recovery of microgram and submicrogram quantities of U by electroplating has been studied, using radioactive U‐233 as a tracer with and without the presence of microgram quantities of natural U as carrier. Optimum results were obtained in an ammonium oxalate medium with electrolysis at 80°–85°C being performed first in acidic solution and then in alkaline solution. A small Pt disk which fitted into a flow counter was used as cathode, and a Pt spiral served as anode. With 20 µg of U carrier present and a volume of 25 ml, an average recovery, based on alpha counting, of was obtained for amounts of U‐233 ranging from 0.03 to 0.13 µg.