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.     

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%.     

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.     

Radiochemical studies on generator eluted113mIn chloride

^113mIn is milked out of a¹¹³Sn-^113mIn generator with dilute hydrochloric acid for use in nuclear medicine. The concentrations of the various impurities like Sn, Zr and their colloidal forms which may trap^113mIn activity have to be initially evaluated before releasing the generator for medicinal use. The authors have evaluated the purity of the^113mIn-chloride obtained from the generators in detail. The possibility of using a mixture of HCl and NaCl as an alternative eluent for^113mIn has also been investigated. It has been observed that this new eluent gives greater yields of^113mIn and renders the final manipulation of isotonicity of indium labelled compounds easy.     

Views on quality tests of radiopharmaceuticals

The quality tests of radionuclides produced from generators (⁹⁹Mo→^99mTc,¹¹³Sn→^113mIn) have been reviewed. The quality controls of radiopharmaceuticals derived from these radionuclides and prepared with the help of ready-for-use reagents assembled in kits have been presented. The possibility of new tests regarding sterility (by means of a radiometric method) and detection of endotoxin (based on gelification of limulus amoebocyte lysate) have been suggested.     

Separation of radioindium (N.C.A.) from neutron irradiated tin and cadmium on hydrated antimony pentoxide

Hydrated antimony pentoxide (HAP) as an absorbent for column operation has been prepared by hydrolysis of SbCl₅ with deionized water. Sorption behavior of Sn, Cd, Sb and In was studied on HAP in HCl medium. Radiochemical separation of no-carrier added^113mIn from¹¹³Sn/¹²⁵Sb and^115mIn from¹¹⁵Cd wa achieved over a HAPO column. The separated products were of high radionuclidic purity.     

Dünnschichtchromatographie als Hilfsmittel in der radiochemie. 6. Mitteilung. 1. Trennung von Sn, 125Sb und 125mTe. - 2. Trennung von As,Sb und Sn

1. Thin-layer chromatography is applied to the separation of the nuclids of the decay-chain: ¹²⁵Sn → ^125mTe. Different factors influencing the separation are investigated. The method can be used for the carrier-free separation of ^125mTe. 2. As, Sb and Sn have been separated by thin-layer chromatography.     

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.     

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.     

Effect of chemical condition of technetium-99m sodium pertechnetate on the active kit components and radiolabeling yield of Tru-Scint® ADTM monoclonal antibody kit

The chemical condition of^99mTc eluate obtained from a⁹⁹Mo-^99mTc generator is a function of the source, time elapsed after elution and age of the eluate. The radiochemical purity and stability of^99mTc labeled MAb-170 (Tru-Scint^®AD^TM, photoactivated monoclonal antibody kit) preparations was evaluated comparing pertechnetate source of known age and elution history. The effect of H₂O₂, a radiolytic impurity in^99mTc eluates, on the active kit components stannous ion and photoactivated MAb and radiolabeling, yield has been investigated. The lyophilized Tru-Scint^® AD^TM kit has been labeled with 20 to 80 mCi in 0.5 to 4.0 ml of Sodium Pertechnetate^99mTc Injection, USP. The eluates were obtained from three brands of generators and used up to six hours after elution. The kits were reconstituted either with Sodium Pertechnetate^99mTc Injection, USP or Sodium Chloride Injection, USP, 0.9% containing known amounts of H₂O₂. The reconstituted kits were analyzed for radiolabeling yield and radiochemical impurities, stannous ion and protein sulfhydryl group. The results indicated that the radiolabeling yield is a function of both the chemical condition of^99mTc eluate, generator brand and the radiolabeling parameters like reconstitution volume and activity. The observed radiolabeling yield differences did not depend on the amount of chemical technetium in the eluate. The major radiochemical impurities at 15-minute post labeling have been identified as the^99mTc-buffer complex and column adsorbed reduced^99mTc (^99mTc-Ad) species and not the unreduced^99mTcO ₄ ^– .     

Subtoichiometric determination of indium and tin by radioactivation analysis

A method of radioactivation analysis has been developed for the determination of indium and tin. It is based on substoichiometric extraction of indium diethyldithiocarbamate into carbon tetrachloride from a slightly ammoniacal solution in the presence of potassium cyanide. With this method, indium can be determined via^116m In (T=54 min) and tin via^113m In (T=104 min) which is formed by the reaction¹¹²Sn(n, ψ)¹¹³Sn. The method has been applied to the determination of indium in metallic zinc and of tin in tin-doped gallium arsenide, and 0.4 ppb of indium was analyzed in a zinc sample.     

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.     

Study of isotope exchange reactions by double labelling

This paper presents the method of double labelling in the study of the kinetics of homogeneous isotope exchange reactions. This method was tested by the determination of the Sn(II)−Sn(IV) exchange rate in hydrochloric acid medium. The system was labelled by the tracer^119mSn [initially in the Sn(IV) state]; when the isotope equilibrium was established, Sn(IV) was again labelled by tracer¹¹³Sn. The separation of Sn(II) and Sn(IV) in the given time of exchange was performed by the extraction of Sn(IV)-hydroxyquinolate into chloroform. The specific activities of the separated components were determined from the ratio of¹¹³Sn and^119mSn activities. The exchange rate was calculated from the time dependence of specific activities. The advantage and possibilities of the method of double labelling in the study of isotope exchange are discussed.     

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.     

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.     

Preparation of113mIn radiocolloid for liver scanning

Kits were developed for the preparation of a sterile^113mIn colloid as a radiopharmaceutical for liver scanning. 2.5 ml of^113mIn sterile generator eluate was added to 0.5 ml of ferric chloride dissolved in 0.04N HCl (40 g/ml). The pH was adjusted by addition of 2 ml of phosphate buffer. The optimal pH for the formation of^113mIn colloid was found to be equal to 7.5–8.5. Liver uptake in mice was determined to be 85–90%.     

The determination of tin in biological samples

A rapid method is described for the determination of tin in biological material, using¹²³Sn (T=40 m). The chemical procedure is based on the nearly quantitative extraction of tetravalent tin into toluene from an acid 1.3M iodide solution. The recovery is determined by spiking the solution with¹¹³Sn and measuring the activity of the^113mIn daughter in the counting sample. The lower limit of the determination is ?0.01μg. Results are given for standard kale powder and dried animal blood.     

Comparative study of different chromatographic methods for quality control of113mIn-radiopharmaceuticals

Paper chromatography and Gel Chromatography Column Scanning technique (GCS) have been applied for the separation of indium fractions in^113mIn-radiopharmaceuticals. By these techniques the percentage of ionic indium,^113mIn-colloid and^113mIn-compound have been determined. The resolution efficiency of the gels was found to be significantly influenced by the gel type media and the pH of the eluent. The results obtained from the GCS-profiles indicated that the Sephadex G-50 Fine was the best and can be routinely used in the radiochemical quality control of the^113mIn-phytate. Good separation of^113mIn-colloids,^113mIn-microaggregate and^113mIn-phytate from carrier-free^113mIn-eluate was performed using Whatman No. 3, previously washed with 0.04N HCl and developed either with 0.9% NaCl (for^113mIn-colloid), or 85% methanol (for^113mIn-phytate), or phosphate-methanol buffer (for^113mIn-microaggregate) as rapid and simple procedure for determination of the radiochemical quality control of indium compound in the forms of radiocolloids.     

Radionuclides used for therapy and suggestion for new candidates

Summary Targeted radiotherapy has the potential to provide radiation doses from a wide range of radionuclides, some of them suitable for killing single cells while others are more suitable for killing tumor cell clusters of various sizes. A list of 64 radionuclides, including 20 new potential candidates for therapy (⁷³Ga, ⁷⁵Se, ^87mSr, ⁹⁷Ru, ¹⁰³Ru, ¹¹³Sn, ^113mIn, ¹¹⁷Sb, ¹²³Sn, ¹³¹Cs, ¹³⁹Ce, ¹⁴¹Ce, ¹⁴⁹Eu, ¹⁶⁷Tm, ¹⁷⁰Tm, ¹⁷³Tm, ¹⁹⁵Au, ^195mPt, ¹⁹⁷Pt and ¹⁹⁷Hg) were analyzed in terms of the suitability of their energies for killing tumor cells which grow as single, small, intermediate and large clusters. In addition, their possible production routes were studied.     

The study of conditions for the preparation and application of99Mo−99mTc generators starting from irradiated molybdenum metal

⁹⁹Mo−^99mTc generators were prepared starting from irradiated molybdenum metal instead of MoO₃ in order to use reactor irradiation space more economically. The adsorption of molybdenum as sodium molybdate on different kinds of alumina was investigated. The effect of the pH of the column and the aqueous phase concentration of molybdenum were studied and related to the elution yield of^99mTc. A study of the radiation damage effect indicated that generators having a high elution efficiency of 90% could be prepared in the 100–600 mCi range. The losses of⁹⁹Mo were minimized to 10⁻⁵-10⁻⁴% and those of alumina to 2–5 μg/ml eluate.