Separation of95Zr and95Nb by means of sorption on silica gel from hydrochloric acid solutions

The adsorption behaviour of zirconium and niobium on silica gel from hydrochloric acid solutions was studied by batch equilibrations and passage through columns. On the basis of this, new methods are suggested for the separation and purification of⁹⁵Zr and⁹⁵Nb in hydrochloric acid and hydrochloric acid—methanol solutions. The methods are comparatively simple and rapid, and both zirconium and niobium can be obtained in a radiochemically pure state.     

The use of hydrochloric acid in separating95Zr−95Nb activity from uranium fission products on silica gel

Dissolution of a neutron-irradiated uranium target in a medium of 6N HCl containing a few drops of very dilute HNO₃ yielded a matrix solution which on running on a silica gel column allowed the complete adsorption of the⁹⁵Zr−⁹⁵Nb activity formed in the fission process. The⁹⁵Zr−⁹⁵Nb activity is cleanly and totally eluted with 0.5% oxalic acid solution. None of the uranium or the activity of the other fission products was found to be adsorbed on the column.     

Separation of zirconium from fission products in silica gel—nitric acid systems

A method for the separation of zirconium from fission products based on the system 100–200 mesh silica gel—2.0 M nitric acid is described. Decontamination factors are over 500 for ⁹⁵Nb, ¹⁰⁶Ru, ¹²⁴Sb, ¹³⁷Cs, molybdate and uranium(VI), and the yield of zirconium is 98 %.     

Selective separation of99Mo from fission products in chloride media on activated alumina

The radioisotope⁹⁹Mo generated through the fission of neutron-irradiated uranium targets was separated in an extremely radiochemically pure state. The target dissolution mixture was run on a silica gel column whereby the⁹⁵Zr−⁹⁵Nb activity, the serious radiocontaminants of⁹⁹Mo, was adsorbed on the gel. The effluent from the gel column was processed and treated with sodium dihydrogen phosphate. The processed solution was run on an activated alumina column whereby⁹⁹Mo was adsorbed as phospho-molybdate complex ion, then desorbed from the column as the molybdate ion by eluting with 10% NaOH solution. By recycling the adsorption and desorption steps on alumnia,⁹⁹Mo was finally obtained totally free from all other radiocontaminants.     

Rapid separation of niobium-95 from zirconium-95 by solvent extraction with α-benzoinoxime

A solvent extraction method is presented for the separation of⁹⁵Nb from⁹⁵Zr.⁹⁵Nb is extracted quantitatively into a chloroform solution of α-benzoinoxime from 5N hydrochloric acid solution. By following the recommended procedure, a separation factor higher than 10⁴ is achieved.⁹⁵Nb can be back-extracted into concentrated hydrochloric acid. The radiochemical purity of the⁹⁵Nb separated has been ascertained by half-life and γ-ray energy measurements. The whole procedure takes less than 20 min.     

Development of a method for the determination of 93Zr and 94Nb in radioactive waste using TEVA® resin

The behaviour of ⁹⁵Zr and ⁹⁵Nb isotopes on TEVA^® resin column was studied. The influence of hydrofluoric, hydrochloric, oxalic and sulphuric acids on the separation and chemical yield of zirconium and niobium was tested. The method is suitable for the separation of ⁹³Zr and ⁹⁴Nb isotopes from hydrofluoric, hydrochloric and sulphuric acid by using different concentrations of the acid for the load or elutes solutions. Samples from reactor and fuel assemblies such as the control-rod connection rod, shielding/absorber parts of fuel rods, neutron in-core measurement channels, pressure vessel basic construction material and internal cladding, core barrel and reactor protection tube unit were analysed.     

Extraction chromatographic separation of uranium and fission products in the system di-(2-ethylhexyl)phosphoric acid-hydrochloric acid

An elution scheme has been developed for obtaining separate fission product and uranium fractions using extraction chromatographic techniques with di-(2-ethylhexyl)phosphoric acid as a stationary phase and HCl of varying concentration as eluting agent. The investigations have been concentrated on the fission products cerium, europium, molybdenum and zirconium. The elution of zirconium by oxalic acid is characterized by a peak broadening and has been explained by considering extraction kinetics. Experiments on column performance with different support materials have proved Ftoroplast-4 and Celite Hyflo Super Cel to be capable of giving column fillings with equal separation ability.     

Selective transport of zirconium (IV) and niobium (V) from hydrochloric media through a bulk liquid membrane

The selective transport of zirconium/niobium from hydrochloric medium has been investigated through a bulk liquid membrane (BLM) using tri-n-butyl-phosphate (TBP), tri-n-octylamine and dibenzo-18-crown-6 (DBC-6) as the extractants (carriers). The Optimization studies have been carried out by scrutinizing the effect of variables such as the hydrochloric acid concentration in the feed solution, membrane type and hydrochloric acid concentration in the strip solution using the Taguchi approach. The Quantitative transport of zirconium/niobium has been observed by 30% (v/v) TBP in 1200 min from the feed composed of a 9.0 M hydrochloric acid solution of Zr(IV), Nb(V) and lanthanide cations, while the transport of other cations, which have been presented along with Zr/Nb are less than 3% during the same time. Moreover, the possible mechanism of Zr(IV)/Nb(V) ion transport through the BLM has also been discussed and the results show a consecutive, irreversible second-order reaction at the interfaces. Transfer kinetics studies show that niobium transfer process exhibits slightly faster kinetics than zirconium.     

Sine-wave polarographic determination of zirconium or niobium in aqueous media

The sine-wave polarographic determination of zirconium in aqueous media was investigated using solutions which were 0.55 – 5.5·10^-3M in zirconyl chloride and 1 M in potassium chloride and had been adjusted to pH 2.0 with hydrochloric acid. It was possible to determine zirconium in the concentration range of 0.05 to 0.4 mg per ml. The sine-wave polarographic behavior of zirconium in aqueous solutions in the pH range 2–3 is discussed. The sine-wave polarographic determination of niobium in aqueous media was investigated using concentrated sulfuric acid containing 5 to 0.1 mg of niobium per ml in a supporting electrolyte of citric acid; the determination of niobium was possible down to 0.1 mg of niobium per ml of concentrated sulfuric acid although the D.C. polarographic method was impractical for the determination of less than 0.5 mg of niobium per ml.     

Determination of calibration curves for <Superscript>131</Superscript>I in thyroid tumour metabolic radiotherapy and other radionuclides used in SPECT imaging

Large columns containing aluminum oxide (Al₂O₃) or gel (e.g. zirconium molybdate) are needed to prepare ⁹⁸Mo(n,γ)⁹⁹Mo→^99mTc column chromatographic generators that results in large elution volumes containing relatively high ⁹⁹Mo impurity and low concentrations of ^99mTc. The decrease in radioactive concentration or specific volume concentration of ^99mTc places a limitation on some pharmaceutical kits (DTPA, MIBI, ECD, etc.) or clinical procedures. We report on the post elution concentration of ^99mTc using in house prepared lead cation-exchange and alumina columns. Using these columns high bolus volumes (10–60 mL 0.02M sodium sulfate) of ^99mTc can conveniently be concentrated in 1 mL of physiological saline. This approach also works very effectively to prepare high specific volume solutions of ^99mTc-pertechnetate from a fission based ⁹⁹Mo/^99mTc generator in the second week of its normal working life.     

Trennschema zur Isolierung von Pu-Np-Zr-Nb-Mo-Tc-Te und U aus Spaltproduktl?sungen

Zusammenfassung Für salzsaure Lösungen bereits bekannte Anionenaustauschertrennungen von Zr-Nb, Zr-Mo und Mo-Tc konnten zu einer Trennung von Zr-Nb-Mo-Tc zusammengefaßt werden, deren quantitativer Verlauf nachgewiesen wurde.Durch Zusatz von Alkohol zu den salzsauren Elutionslösungen konnte ein Trennungsgang zur Isolierung von Zr, Nb, Mo, Tc und U aufgestellt werden. Die Elemente werden aus hochmolarer Salzsäure adsorbiert und durch stufenweise Elution mit gemischten Lösungsmitteln sinkender Gesamtacidität getrennt. Tc, das mit Salzsäure oder Mischungen aus Salzsäure und Alkohol nicht desorbierbar ist, wird mit Salpetersäure eluiert.Es konnte gezeigt werden, daß Te in das Trennschema zur Auftrennung von Zr, Nb, Mo, Tc und U eingefügt werden kann. Eine Trennung von Np und Zr innerhalb des Trennschemas — also durch Adsorption aus hochmolarer Salzsäure und stufenweise Elution — war wegen der Ähnlichkeit der Verteilungskoeffizienten von Np und Zr nicht möglich. Es konnte jedoch eine Vortrennung in eine kleine Np-Fraktion und eine stark mit Np verunreinigte Zr-Fraktion erreicht werden. Für die Nachtrennung von Np und Zr wurde ein bei kleinen HCl-Molaritäten gefundenes Maximum des Verteilungskoeffizienten von Np^V ausgenützt, das eine Trennung beider Elemente durch Aufbringen aus 1,3 m Salzsäure auf den Anionenaustauscher ermöglicht. Zr wird nicht adsorbiert. Np bricht erst mit einer größeren Elutionsmenge 1,3 m Salzsäure durch. Da der ausgearbeitete Trennungsgang an die bereits bekannte Elution des Pu mit 12 m Salzsäure (unter Zusatz von NH₂OH · HCl und NH₄J) angeschlossen werden kann, war es möglich, ein Trennschema aufzustellen, das die Isolierung von Pu, Np, Zr, Nb, Mo, Tc, Te und U aus Spaltproduktlösungen gestattet.

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Summary A procedure has been worked out for the total separation of Zr-Nb-Mo, and Tc by anion-exchange in hydrochloric acid solutions using known single separations of Zr-Nb, Zr-Mo, and Mo-Tc, and proved to be quantitative.Utilizing hydrochloric acid solutions containing alcohol as eluents, a method for the separation of Zr-Nb-Mo-Tc, and U has been developed. Highly concentrated hydrochloric acid solutions of these elements are added to the resin column and eluted sequentially with mixed solvents of decreasing over-all acidity. Tc is not desorbed with hydrochloric acid or mixtures of hydrochloric acid and alcohol; it is removed from the column with nitric acid. Investigations indicated that the separation of Zr-Nb-Mo-Tc-U, and Te is possible. Experiments to include Np in the sequential separation scheme developed, did not yield satisfying results because of the similarity of the elution curves of Zr^IV and Np^V. The eluted Zr was contaminated with Np and required further purification. Based on the measurement of the distribution coefficients of Np^V in hydrochloric acid solutions, showing a maximum of adsorption at low concentrations of hydrochloric acid, a method for the separation of Zr from Np has been developed. The elements in 1.3 M HCl solution are added to the resin column; Zr is not absorbed. The elution is continued with 1.3 M HCl solution to remove Np, which is eluted only with larger volumes of this acid.Since Pu can be removed from the resin column with highly concentrated hydrochloric acid solutions prior to the other elements, the sequential separation scheme makes possible the isolation of Pu-Np-Zr-Nb-Mo-Tc-Te, and U from fission product mixtures.

     

Use of alcoholic solutions for the isolation and purification of americium and curium with anion-exchangers

The sorption of transplutonium (TPE), rare-earth (RE) and other elements by anion-exchangers (Dowex 1 type) from aqueous alcoholic solutions of nitric acid and ammonium thiocyanate was investigated. This investigation allowed the development of simple and effective methods of americium—curium separation from frradiated plutonium. Plutonium, TPE (in a +3 oxidation state) and RE are firmly sorbed by the anion-exchanger from 1 M HNO₃ in 90% alcohol, Fe, Al and fission products Cs, Sr, Nb, Zr, and Ru pass through the column under these conditions. The RE separation from TPE is achieved by washing the column with 0.5M NH₄SCN in 80% alcohol. The column is then washed with 0.5 M HNO₃ in 85% alcohol, and americium—curium separation proceeds. Use of this method for recovery of an irradiated plutonium target containing 100 mg Pu, Am and Cm is described.     

Séparation chromatographique des lanthanides en deux groupes basée sur des différences dans la cinétique de décomposition des complexes lanthanides-macrocyclesChromatographic separation of lanthanides into two groups based on kinetic differences in the decomposition of macrocycle/lanthanide complexes

The separation of the lanthanides in two groups, based on differences in decomplexation rates of the LnDOTA entities (DOTA = 1,4,7,10-tetraazacyclododecane-N,N′,N″,N?-tetraacetic acid), is achieved on a sulphonate cation-exchange column (H⁺ form). The yttrium earths, from terbium to lutetium, are eluted first as Ln-DOTA-H species with 1.25 M HCl; the light lanthanides, from lanthanum to samarium inclusive, are eluted as uncomplexed ions at the end of the chromatogram, with more concentrated hydrochloric acid. Given an equimolar mixture of the Eu-DOTA and Gd-DOTA complexes as starting solution, 40% of the gadolinium can be recovered free from europium at the start of elution and 47% of the europium free from gadolinium at the end of the elution.     

Separation of zirconium and hafnium from early actinides and rare earth elements with eichrom’s pb resin in HCl

The separation of zirconium and hafnium isotopes from the early actinides and rare earth elements (REE) with Eichrom’s Pb resin has been studied. Batch studies were performed to characterize the behavior of actinium, thorium, zirconium, hafnium, lutetium, and yttrium on Pb resin from HCl solutions (0.001 M to 11 M). The early actinides and REE had no affinity for the resin at any concentration of HCl, but zirconium and hafnium showed a moderate uptake at high concentrations of HCl with a maximum extraction at 11 M HCl. Several column separations were tested, including with only tracer isotopes and with mass. Rapid, simple separations of zirconium from actinium, thorium, protactinium, and the REE with high yields and low elution volumes are presented with applications for tracer isotope production and fission product separations. The resin is less suitable for hafnium separations as hafnium tends to bleed off the resin even at high concentrations of HCl.

     

Separation of carrier free95mTc from niobium targets irradiated with alpha-particles

A^95mTc tracer with an excellent quality was prepared by a simple sublimation method after α-bombardment of niobium metal. Technetium-95m produced by the⁹³Nb(α,2n)^95mTc reaction was separated from the niobium targets in a quartz tube by heating at 1100°C in an oxygen gas flow. Technetium-95m sublimed as an oxide was deposited on the inner wall of the quartz tube outside an electric furnace, and then collected as a pertechnetate solution by washing with water. The ICP-MS analysis of the^95mTc solution revealed its excellent quality, compared to a^95mTc solution prepared from the same targets through a wet chemical separation method and a commercial^95mTc solution. With this tracer, the precision of ICP-MS analysis of⁹⁹Tc in environmental samples are highly improved.     

Determination of microamounts of zirconium(IV) and titanium(IV) with preliminary TLC separation

By the application of thin-layer chromatography on silica gel H and the solvent system consisting of 6 M HCl:acetylacetone: 9 M H₂SO₄ (60:2:1, v/v/v), zirconium and titanium have been quantitatively separated from each other, as well as from numerous other interfering ions. The efficiency of the chromatographic separation was evaluated by semiquantitative determination of zirconium and titanium by visual colorimetry of spots in situ, as well as by spectrophotometric determination of zirconium with rutin after its elution from silica gel H thin-layer.     

Chemical separation of molybdenum from uranium and fission product nuclides

A very rapid method for the separation of molybdenum(VI) from neutron irradiated uranium and its fission products is described. The procedure is based on the selective extraction of molybdenum(VI) by a 0.1M solution of 2-hexylpyridine in benzene from 4M HCl+0.04M KSCN. Decontamination factors were estimated to be >10⁴ for the radionuclides of niobium, zirconium, ruthenium, lanthanum, cerium, promethium, yttrium, strontium and barium.     

Solvent extractions of zirconium and niobium from HCl solutions by Aliquat 336/Alamine 336 and DOSO mixtures

Liquid-liquid extractions of zirconium(IV) from aqueous HCl solutions by mixtures of Aliquat 336 or Alamine 336 and diocytl sulfoxide (DOSO) in the diluent benzene has been found to be always higher than that by any single extractant. While the cationic extractants extract Zr(IV) above 6M HCl, DOSO extracts from 4M onwards. Synergism has been observed in all cases. With any of these extractants extraction becomes almost quantitative at and above 10M HCl, but with mixtures of the cationic and neutral extractants, extraction is quantitative in the range 8–9M HCl. Although the extracted species with DOSO alone seems to be ZrCl₄·DOSO, with the mixture of extractants, however, the extracted species appear to be Q₂ZrCl₆·DOSO where Q is R₃ ⁺NH (for Alamine 336) and R₃ ⁺N(CH₃) (for Aliquat 336). Studies on separation of⁹⁵Zr–⁹⁵Nb pair from aqueous HCl media by Alamine 336 or DOSO and their mixtures in benzene exhibit preferential extraction of⁹⁵Nb leaving behind⁹⁵Zr in the aqueous phase, and extractions have been found to depend both upon the extractant and HCl concentrations.     

Chromatographic isolation of144Ce and144Pr from the wastes of irradiated uranium treatment

A two-step chromatographic technique was elaborated to isolate¹⁴⁴Ce,¹⁴⁴Pr from a solution of uranium fission products in 6M HNO₃. The oxidation to Ce(III) by bromate and selective adsorption of¹⁴⁴Ce(IV) on anion exchange column were used to concentrate and purify¹⁴⁴Ce. Some impurities of uranium,⁹⁵Zr,⁹⁵Nb,¹⁰⁶Ru remain in¹⁴⁴Ce solution after the first step of its isolation. The final purification is achieved by passing the 6M HNO₃ solution of¹⁴⁴Ce(IV) through the HDEHP-coated teflon column. The decontamination factors of¹⁴⁴Ce from main fission products are given. 7.2 mCi of (¹⁴⁴Ce+¹⁴⁴Pr) are recovered from each gram of irradiated uranium trioxide with the yield greater than 99%. An improvement of known generator was carried out to elute a purer¹⁴⁴Pr from maternal¹⁴⁴Ce(IV) adsorbed on the anion exchange column.     

Zur Abtrennung und Dekontamination von Uran aus salpetersauren Spaltproduktlösungen mit Anionenaustauschern

Weight distribution coefficients for U(VI) against Dowex 1 and Dowex 2 in HCl/HNO₃ and practical column-exchange capacities under defined conditions were determined. The behaviour of thorium, protactinium, iron, zirconium, niobium, ruthenium, and tellurium in the same system was studied in column experiments. The results of these determinations are discussed. An ion exchange procedure for enrichment and decontamination of uranium from fission products and thorium containing nitric acid solutions with the aid of a simple remoted handling apparatus is described.