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%.     

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.     

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.     

<Superscript>137</Superscript>Cs/<Superscript>137m</Superscript>Ba radioisotope generator based on 6-tungstocerate(IV) column matrix

Summary Barium-137m radioisotope generator of the chromatographic column elution mode based on loading 1.5 g 6-tungstocerate(IV) gel matrix with ~54 kBq of fission-produced ¹³⁷Cs is described. The elution performance of the generated ^137mBa radionuclide was investigated as a function of chemical composition of the eluent, flow rate, elution frequency, and age of the generator system. At comparable conditions, ^137mBa eluates with 0.9% NaCl-0.1M HCl eluent had higher elution yields and radionuclidic purity than with 0.1M NH₄Cl-0.1M HCl eluent. The generator has been repeatedly eluted for 311 days by passing 4810 ml of the saline eluent (10 ml × 481 elution operations) at a flow rate of 3.0 ml/min. Barium-137m eluates of high and reproducible elution yields, chemical and radionuclidic purities of (≥ 99.99%) were obtained.     

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.     

Study on the preparation of a137Cs/137mBa radionuclide generator

^137mBa has been applied successfully to dynamic studies for diagnosis in nuclear medicine for a long time. A variety of inorganic exchangers have been employed for the separation of^137mBa from its parent¹³⁷Cs. In the present study, cupric cobaltic ferrocyanide and amorphous zirconyl phosphate were synthesized and compared for use in a¹³⁷Cs/^137mBa generator. The results show that the former can adsorb¹³⁷Cs more efficiently and provide high elution yield of^137mBa with greater than 99.99% radionuclide purity. A new generator involving multimillicuries of^137mBa, in connection with a computerized detection system, has been constructed.     

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.     

Development of a 212Pb and 212Bi generator for homolog studies of flerovium and moscovium

A simple generator using AG 50Wx8 cation exchange resin has been developed for continual elution of ²¹²Pb and ²¹²Bi from the parent radionuclide ²²⁸Th, derived from ²³²U. Using 0.4 M HCl as an eluent will elute ²¹²Bi while ²¹²Pb is eluted with 2 M HCl. The generator has shown good reproducibility of elution bands. A generator set-up in 2013 has been in continual use over 4 years demonstrating that this generator system has a long and stable lifetime. The generator system presented here has served as a long-term method for attaining no-carrier-added ²¹²Pb and ²¹²Bi radionuclides for homolog studies of flerovium and moscovium.

     

Heterogeneous isotope exchange reaction between SnCl2 and SnO2·xH2O in HCl medium

Heterogeneous isotope exchange between hydrated stannic oxide and stannous chloride in 0.1M HCl solution has been studied as a function of the stannic oxide, stannous chloride, and chloride ion concentrations, and temperature. The exchange process is a second-order reaction, which is independent of the chloride ion concentration, with a mean rate constant, k, of 2.31 dm³ mol^–1·min^–1. The activation energy of the isotope exchange process was found to equal 3.62 kcal·mol^–1. Possible use of this system, SnCl₂/SnO₂·xH₂O, as basis for a¹¹³Sn-^113mIn generator is suggested.     

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.     

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).     

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%.     

Preparation of a118Te/118Sb radionuclide generator

The development of a new radionuclide generator, based on¹¹⁸Te/¹¹⁸Sb, has been studied. The 3.5 minute¹¹⁸Sb daughter activity decays principally by positron emission and has potential use as a flow tracer. The¹¹⁸Te parent is conveniently produced by proton bombardment of antimony targets. A simple and efficient scheme for the separation of radiotellurium from proton-irradiated antimony targets has been developed, and thin-target cross sections for¹²¹Sb(p, 4n)¹¹⁸Te and competing reactions have been determined. For antimony targets irradiated with 46 MeV protons, the yields (mCi/g Ah) of¹¹⁸Te,^119mTe and¹¹⁹Te were measured to be 0.71, 0.33 and 1.9, respectively. The adsorption and elution characteristics of activated carbon for tellurium have been evaluated for use as a column chromatography adsorbent in a¹¹⁸Te/¹¹⁸Sb generator. The conditions for optimal¹¹⁸Sb elution and minimal¹¹⁸Te breakthrough for promising systems are presented.     

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.     

Comparative quality control of some bone-seeking99mTc radiopharmaceuticals by gel chromatography

The radiochemical purity of the three osteopatic ligands:^99mTc(Sn)-PyP,^99mTc(Sn)-DPD and^99mTc(Sn)-MDP has been determined by gel chromatography on Sephadex. The results of the analyses strongly depend on the composition of the eluent. The dilution effect of pure saline as eluent was observed in all the preparations examined. The most sensitive was found to be^99mTc(Sn)-PyP. The retention of^99mTc activity bound to the gel matrix (^99mTc-hydrolyte) was over 30%. The diphosphonates were found to be more stable (retention 10–15%). The retention is substantially lower, i.e. a high recovery of the labeled complexes is obtained when the eluent contains the ligand. The best results are obtained when the eluent contains the same concentrations of ligand and reductant as in the labeled complex. There was no significant difference in the behavior of the given radiopharmaceuticals prepared as a fresh solution and in the freeze-dried kit.     

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.     

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.     

Comparative study of different gels for quality control of99mTc-radiopharmaceutical kits

The available six types of Sephadex and one type of Sepharose have been applied in the separation of technetium fractions in^99mTc-labelled radiopharmaceuticals produced in our laboratory using the GCS technique. By this technique the chemical state and the percentage of^99mTc-fractions have been determined. The resolution efficiency of some gel types were found to be significantly influenced by the pH of the eluent. The results obtained from the experiments indicated that Sephadex G-25 Fine was the best and can be routinely used in the radiochemical analysis of the following kits:^99mTc-HSA,^99mTc-DTPA and^99mTc-HIDA and G-100 for^99mTc-PYP. With^99mTc-HSA and^99mTc-PYP kits, 0.9% NaCl eluents at pH 3.2 and pH 2 to 2.5, respectively, were found to be necessary for the separation of^99mTc-fractions. G-50 Fine was found to be the best gel between the others in the separation of^99mTc-fractions in testing of the weak radiopharmaceuticals,^99mTc-GH and^99mTc-MDP. The development of^99mTc-MDP with the eluent at the same pH as the preparation gives negligible interaction effect.     

Radiochemical separations by adsorption on some oxides of groups IVB and VB

The interactions between titanium dioxide, niobium pentoxide and tantalum pentoxide and 55 elements have been studied by batch experiments in nitric acid. The variation of the distribution ccefficients with nitric acid concentration is presented and discussed. The adsorption mechanism for some ions has also been investigated. Column experiments have been carried out to check the practical use of the investigated oxides in radiochemical separations. A^99mTc generator based on the use of TiO₂ is also presented.     

Characteristics and behavior of a99Mo/99mTc generator using irradiated titanium molybdate as column matrix

A⁹⁹Mo/^99mTc generator, system was made with a performed titanium molybdate gel. The irradiation was carried out at a medium neutron flux of 1.5×10¹³ n cm^–2·s^–1. The irradiated matrix was loaded on top of a column composed of hydrous zirconium oxide alumina. The elution efficiency and the amount of total technetium per mCi^99mTc in the generator eluents have been determined. Molybdenum breakthrough has also been determined and compared with literature values. The influence of the particle size, water content, neutron flux and molybdenum content on the total^99mTc-activity has been investigated.