Simple indium generators

Very economical, rapid and pure methods for the production of^115mIn and^113mIn from¹¹⁵Cd and¹¹³Sn, respectively are described. The methods are based on the extraction of^115mIn by o-xylene from 7.2M H₂SO₄ −0.06M HBr, and its reextraction with ≈11M H₂SO₄ −0.06M HBr from n-hexane. The γ-spectra of the generated^115mIn and^113mIn indicate that they are free from any other interferences.     

Separation of trace elements,In(III), Sn(IV), Sb(V) and Te(IV) by adsorption on activated carbon and graphite

Adsorption behaviour of trace elements, In(III), Sn(IV), Sb(V) and Te(IV) on activated carbon and graphite powder was studied. Adsorption characteristics of the ions enabled the separation of In(III)–Sn(IV), Sn(IV)–Sb(V) and Sb(V)–Te(IV) pairs. Applications to practical separation, milking of^113mIn from¹¹³Sn, removal of tin impurity from¹¹⁹Sb, and milking of¹¹⁹Sb from^119mTe, are presented.     

Separation of carrier-free115mIn from115Cd and132I from132Te over the zirconium oxide column

A new way of radiochemical separation of carrier-free^115mIn from¹¹⁵Cd and¹³²I from¹³²Te over the column of zirconium oxide is described. Activities of Cd and In in equilibrium in dilute acetic acid solution were bufferred with dilute sodium acetate and fed into the column at a pH 7, when cadmium activity passed out unadsorbed and the^115mIn was adsorbed in the column. A study of the γ-ray peak of the separated^115mIn showed that the product is of high radionuclidic purity. Te-I pair was separated by passing the weakly acidic solution of¹³²Te and¹³²I in the presence of AgNO₃ and Na₂SO₃, through the column where both activities were adsorbed. Iodine was washed outh with 5% sodium thiosulphate solution and the retained tellurium activity was later washed out with 6M HNO₃. The β-decay study showed that the separated¹³²I product is of high radiochemical purity. The processes took less than half an hour and the yields were quantitative.     

Separation of tin from some metals by extraction chromatography

Much attention has been devoted to Sn (IV) strongly retained on the TBP-Daiflon column from 2M HCl in extraction chromatography. The separations of Sn?Cu, Zn, As, Cd, Sb, Pb,¹¹³Sn-¹²⁵Sb,¹¹³Sn-^113mIn (^113mIn milking) and Sn?Hg?Fe were successfully achieved without any contamination. In the separations, except for the last, only tin was retained separately on the column upon passing the mixed solution. The daughter indium was eluted with 0.5M HCl. In the last separation, iron was eluted with 0.5 M HCl, tin with 0.1M HCl and mercury with 2M HNO₃, for these metals retained on the column. Radioactive tracers for tin, iron, mercury and antimony were used.     

Separation of <Superscript>113m</Superscript>In from <Superscript>113</Superscript>Sn based on activated carbon used as column matrix

The activated carbon was prepared by using corncobs and characterized by sorpatometer for using as an exchanger material to separate the generated ^113mIn from ¹¹³Sn and ^124,125Sb. To optimize the separation process, the different parameters like acetone percentage, HCl concentration were studied. The exchange capacity of Sn(IV) is 7.6 meq/g onto the activated carbon and the elution efficiency of ^113mIn > 80% by using 10 mL of 0.2 M HCl-80% acetone with flow rate 1 mL/min. The radionuclidic purity and radiochemical purity of the eluted ^113mIn were examined and clarified the presence of ^124,125Sb with relatively high level as radio impurities, so further separation was carried out by using Dowex 1×8 as an anion exchanger below the activated carbon matrix on the same separation column to adsorb the ¹¹³Sn and ^124,125Sb, which escape from the activated carbon matrix.     

Adsorption of several tracer cations and separation of234Th from238U and113mIn from113Sn on tin dioxide

The uptake of 22 cations at tracer concentrations has been studied over hydrous tin dioxide exchanger material. A granular variety of tin dioxide was prepared from the reaction of tin(IV) chloride with NaOH solution, and the formula of the material was ascertained to be SnO₂·1.7 H₂O. Radiochemical separation of carrier-free²³⁴Th from²³⁸U and^113mIn from¹¹³Sn was achieved over a tin dioxide column. The separated products were of high radionuclidic purity. The overall separation procedures are very simple and quick with quantitative yield.     

Role of stannic phosphate in the uptake of cations. Separation of zirconium from thorium and cadmium from indium at tracer concentrations

The uptake of Na⁺, K⁺, Rb⁺, Cs⁺, Ag⁺, Ca²⁺, Cu²⁺, Sr²⁺, Cd²⁺, Ba²⁺, Pb²⁺, Sc³⁺, Co³⁺, Y³⁺, Sb³⁺, Tb³⁺, Zr⁴⁺ and Th⁴⁺ cations at very small concentrations has been studied over a column of stannic phosphate. The exchanger was prepared by mixing H₃PO₄, NaCl and SnCl₄ in suitable proportions and the ratio of PSn, in the product was obtained to be 1.96. Radiochemical separations of carrier free⁹⁵Zr from²³⁴Th and^115mIn, from¹¹⁵Cd have been carried out by adopting a simple chemical procedure over a column of stannic phosphate. The -spectrum analysis showed that the separated products are of high radionuclidic purity. The separation procedures took less than half an hour with quantitative yield.     

Mössbauer study of defect119Sn atoms with ligands from silver to iodine

Mössbauer emission spectra of defect¹¹⁹Sn atoms arising from¹¹⁹Sb were measured in InSb, GaSb, CdSb, ZnSb, In₂Te₃, CdTe, and Ag₂Te labeled with¹¹⁹Sb or its parent^119mTe. Together with the results of our previous studies, the isomer shifts of defect and normal¹¹⁹Sn were shown to correlate with the electronegativity of ligands from silver to iodine.     

113Sn-113mIn generator with a glass beads column

The adsorption characteristics of ¹¹³Sn(IV) and ^113mIn(III) on glass beads from NaCl solutions have been studied. On the basis of these studies, ¹¹³Sn-^113mIn generator has been prepared by adsorbing ¹¹³Sn on the glass beads column. ^113mIn has been eluted by the 0.16M NaCl solution with pH 3.0, remaining ¹¹³Sn adsorbed on the glass beads. The yield of ^113mIn has been about 73% in the first 6 ml of eluate, while the breakthrough of ¹¹³Sn has been about 0.042%.     

115Cd photonuclear production for115Cd−115mIn generator

Production of¹¹⁵Cd by means of photonuclear reaction and preparation of a^115mIn generator, based on the genetic sequence of¹¹⁵Cd^115mIn, were studied. The production rates of¹¹⁵Cd by the¹¹⁶Cd(γ, n)¹¹⁵Cd reaction were determined as a function of the maximum bremsstrahlung energies between 35 and 60 MeV. Then the parent,¹¹⁵Cd, was produced by irradiating about 0.15g of CdO with the bremsstrahlung from a 60 MeV-150 μA electron beam. After the parent in the Cd ₄ ²⁻ form was adsorbed on the Dowex 1x8 resin column, the daughter was eluted with a physiologic saline adjusted to pH 1. The generator was milked over a period of 3 days, during which time about 900 ml of eluent were allowed to flow through the column. Even after the milkings were repeated 15 times with 60 ml of the eluent, no¹¹⁵Cd was found in the^115mIn fractions (the detection limit of inactive cadmium: 0.02 μg).     

Separation of113mIn from113Sn on an isotope generator with inorganic ionite

A method of preparation of hydrated zirconium oxide suitable for^113mIn generators was elaborated. A good separation of^113mIn from¹¹³Sn was obtained in the course of routine use of generator, with a very small admixture of zirconium in the eluate.     

Etude des generateurs d'indium-113m

Methods are proposed for the determination of¹¹³Sn in the eluate of an^113mIn generator as well as for the analysis of its chemical and radionuclidic purity. Two generators of different origin have been studied. The presence of the radioisotopes¹¹³Sn,¹²⁵Sb,^125mTe and the elements Zr, Si and Fe have been found in the eluate. Recommendations are given for the use of such generators.     

Zirconium silicotungstate matrix as a prospective sorbent material for the preparation of <Superscript>113</Superscript>Sn/<Superscript>113m</Superscript>In generator

The zirconium silicotungstate (ZrSiW) was studied as an effective sorbent material to be used in the ¹¹³Sn/^113mIn generator. The results elucidated that the distribution coefficient of ¹¹³Sn (3700 mL/g) is greater than ^113mIn (275 mL/g) from 0.1 M HCl acid solution to the ZrSiW material. The maximum sorption capacity of Sn (IV) was found to be 33 mg per gram ZrSiW (~?0.3 mmol/g). The elution yield of ^113mIn was found to be >?78?±?6.4% with an acceptable purity of radionuclidic and radiochemical (≥?99.99 and 96.8%, respectively). The rigorous separation of ^113mIn from the ¹²⁵Sb was carried out due to its long half-life (2.758 years) and beta emission that causes tissue damage. Zr, W and Si levels are below the permitted limit in the ^113mIn eluate.     

Production of no-carrier-added <Superscript>117m</Superscript>Sn from proton irradiated antimony

A method for production of no-carrier-added ^117mSn (NCA ^117mSn) has been developed. It includes proton irradiation of thick antimony targets and chemical recovery of ^117mSn by extraction of Sb with dibutyl ether and chromatographic purification on silica gel column. The method provides production of curie amounts of ^117mSn with specific activity about 1000 Ci/g and high radionuclidic purity.     

Potential use of tungstocerate matrices on the separation of <Superscript>113m</Superscript>In from <Superscript>110m</Superscript>Ag relevant to the separation of the cyclotron-produced <Superscript>111</Superscript>In from its silver target

A procedure for separation of no-carrier-added ^113mIn(III) radioisotope from a bulk of ^110mAg has been developed. The sorption behavior of ^113mIn(III) and ^110mAg(I) ions in HNO₃ acid solutions on different tungstocerate matrices showed high affinity of ^110mAg(I) ions towards tungstocerate(IV) gel matrices compared with ^113mIn(III) ions. No-carrier-added ^113mIn radionuclide was separated from ^110mAg on 12-tungstocerate(IV) column matrix. 11 mL 0.3M HNO₃ acid solution was enough for eluting the ^113mIn from the column bed. ^110mAg was recovered from the column by eluting the column bed with 12 mL 2M HNO₃ acid solution.     

Ceric tungstate as sorbent for polyvalent tracer cations and as an ion exchanger for separation of carrier-free95Nb from95Zr and113mIn from113Sn

The uptake of a few polyvalent ions Ca²⁺ Cu²⁺, Zn²⁺, Cd²⁺, UO²⁺, Cr³⁺, Y³⁺, Ce³⁺, Nd³⁺, Sm³⁺, Tb³⁺, Tm³⁺, Yb³⁺, Lu³⁺, Zr⁴⁺, Hf⁴⁺, Sn⁴⁺, Nb⁵⁺, Se⁶⁺, Mo⁶⁺ and W⁶⁺ at very small concentrations has been studied over ceric tungstate exchanger. A good column variety of the material was prepared by mixing ceric sulphate in 2N H₂SO₄ and aqueous solution of sodium tungstate in suitable proportion. The ratio of cerium: tungstate was obtained to be 11. Separation of carrier-free⁹⁵Nb from⁹⁵Zr and^113mIn from¹¹³Sn have been carried out by applying a very simple chemical procedure over the column of ceric tungstate. The -spectrum of separated⁹⁵Nb and^113mIn products were found to be of high radionuclidic purity. The separation procedure took less than 15 min and the yields were close to 100%.     

Studies on the selectivity of Na+ separation on specially prepared hydrated antimony pentoxide

The selectivity of Na⁺ separation on especially prepared hydrated antimony pentoxide (HAP) was studied with respect to trace elements. For this purpose NaCl samples, doped with 0.5 μg each of altogether 21 selected elements in form of suitable neutron activated compounds, were in relation to practice subjected to column experiments. In some cases trace elements were used in different oxidation states. Considered were elements which are of particular interest for neutron activation analysis. With simultaneous retention of Na⁺ (DK≥10⁸) Cs, Ba, Sc, La, Ce, Eu, Cr, Mo, Mn, Co, Cu, Ag, Au, Zn, Cd, Hg, and Sb are completely eluted from the HAP column, using 7.5N HCl, whereby Cs and to some extent Ba and Sc in comparison to the elements mentioned above required a higher elution volume. Rb, Se and As on the contrary were almost quantitatively retained on HAP column, W partly as WO ₄ ^2? . The scope of validity of the results will be discussed.     

Separation of In3+ from Cd2+ on crystalline antimonic acid.115Cd−115mIn generator

The distribution coefficients of Cd²⁺ and In³⁺ on crystalline antimonic(V) acid (C-AA) have been determined in order to find the best conditions for separation of both cations. Very high affinity of C-AA for Cd²⁺ ions enables to separate^115mIn from¹¹⁵Cd in a single-step rapid procedure. The indium fraction obtained was very pure; the amount of radioactive contaminants was less than 0.0005%.     

Interferences in the determination of trace elements in high-purity tin

Reactor neutron activation analysis of antimony, indium and cadmium in high-purity tin is interfered with by nuclear reactions on the tin matrix. For a number of interfering reactions the cross-sections were determined. The following results were obtained:¹²²Sn(n,γ)^123mSn:σ_th=0.145 barn, I=0.79 barn;¹²²Sn(n,γ)¹¹³Sn:σ_th=0.52, I=25.4 barn;¹¹²Sn(n, 2n)¹¹¹Sn: microbarn;¹¹⁸Sn(n, α)¹¹⁵Cd: microbarn; and¹¹⁴Sn(n, p)^114m1In: microbarn.     

Dünnschichtchromatographie als Hilfsmittel in der Radiochemie. 4. Mitteilung Trennung von 113Sn und 113mIn

Thin-layer chromatography is applied to the separation of ^113mIn from ¹¹³Sn. Different factors influencing migration and separation of the ions are investigated. The method can be used for the examination of the purity of isolated ^113mIn solutions.