113mIn radioisotope generator system

Tin-indium generator systems were made with commercial hydrated zirconium oxide, silica gel and hydrated zirconium oxide prepared by the AMPHLETT method. The adsorption capacity of tin has been determined by both spectrophotometric analysis and gammaspectrometry. Zirconium break-through has been determined and compared with the literature values. The dependence of the adsorption capacity on the particle size has been investigated. The effect of autoclaving on the generator systems has been examined.     

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%.     

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.     

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%.     

Purete radiochimique du complexe113 mIn,acide diethylene-triamino pentaacetique

The radiochemical purity of the¹¹³ mIn-DTPA complex is determined by two methods whose principle is different: filtration on ‘Sephadex” gel, and ascending paperchromatography. The two techniques give slightly different values for non-complexed indium; any way less than 5% mean value. They show that the reproducibility of the method used to prepare the compound is satisfactory.      

Preparation of113mIn and99mTc-microaggregated human serum albumin for liver scanning

Higher than 90% of^113mIn radioactivity was bound to microaggregates. The liver uptake in mice was (80%) with low lung uptake (1.3%). With respect to^99mTc-microaggregated albumin, the radiochemical yield was higher than 95%. The liver uptake in mice was about (80%) with low lung uptake (1.7%). The stability of the microaggregates was followed for two months.     

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.     

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.     

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).     

Methods for radiochemical and radionuclidic purity determination of some99mTc and113mIn radiopharmaceuticals

In order to determine the radiochemical impurities in pertechnetate solution as well as that of unbound^99mTc in its colloid and complex compounds, in indium chloride solution and related compounds, paper chromatography on Whatman No. 1, thin-layer chromatography on silica gel plates, and paper electrophoresis were applied. A simple method for the determination of radionuclidic purity was developed.     

Radiochemical studies on the separation of cobalt with sodium alginate

⁶⁰Co was used as indicator for studies on the separation of cobalt with sodium alginate. Effect of eight experimental parameters (digestion time, digestion temperature, mode of separation, concentration of reagents, pH, order of heating, ammonia, mixing of reagents) on the precipitation and separation of cobalt alginate have been investigated.     

Separation of no-carrier-added 113,117mSn and 113m,114mIn from alpha particle irradiated natural cadmium target

A natural cadmium foil was irradiated by 42 MeV α-particles to produce ^113,117mSn, ^{111,113m,114m}In simultaneously in the target matrix. After the complete decay of short lived radionuclides, long-lived NCA products were separated sequentially from the bulk cadmium by liquid–liquid extraction using di-(2-ethylhexyl)phosphoric acid (HDEHP) dissolved in cyclohexane as organic phase and HCl as aqueous phase. At the optimum condition, 10^?2 M HCl and 5 % HDEHP, NCA In along with NCA Sn radionuclides (75 %) were separated from the bulk Cd resulting to high separation factors of 2.7 × 10⁴ (D _In/D _Cd) and 500 (D _Sn/D _Cd), respectively. The NCA In was stripped back completely to the aqueous phase by 6 M HCl leaving NCA Sn in the HDEHP phase with a separation factor (D _Sn/D _In) of 3.94 × 10⁶.     

Radiochemical studies of some separation methods for phosphorus

Various methods of radiochemical separation were tested for the determination of phosphorus in metals and alloys by neutron activation analysis. Classical methods of separation revealed some defects when they were applied to this problem. Methods using liquid extraction gave low yields and were not reproducible. Methods based on precipitation gave better results, but were not selective enough in most of the cases. Retention on alumina was not possible without preliminary separations We studied a new radiochemical separation based on the extraction of elemental phosphorus in the gaseous phase after reduction at high temperature with carbon. Measurements with radioactive phosphorus showed that the extraction yield is better than 99%.     

Radiochemical studies of the heaviest elements at JAEA

Chemical studies of the heaviest elements in liquid phases at Japan atomic energy agency (JAEA) are reviewed. From the systematic investigation of ion-exchange chromatographic behavior of element 104, rutherfordium (Rf), based on an atom-at-a-time scale, it has been found that the properties of Rf are quite similar to those of the group-4 homologs, Zr and Hf, in the formation of chloride, nitrate, and sulfate complexes, although there are some differences in complexation strength between Rf and the lighter homologues. On the contrary, fluoride complex formation of Rf is significantly different from that of the homologues. Anionic fluoride complexation of element 105, dubnium (Db), has also been studied. The result clearly demonstrates that the fluoride complex formation of Db is considerably different from that of the group-5 homologue Ta, while the behavior of Db is similar to that of the lighter homologue Nb. A new electrochemical approach to the heaviest elements has been successfully conducted by a flow electrolytic column chromatographic method; the oxidation state of element 102, nobelium (No), with single atoms can be controlled with the developed apparatus. Prospects for the future studies on chemical properties of the heaviest elements at JAEA will be briefly considered.     

Radiochemical studies on charge and mass distribution in medium energy fission

Present status of work on charge and mass distribution in medium energy fission of compound nuclei produced using various target projectile combinations is reviewed. Systematics of charge distribution parameters and their dependence on excitation energy of the fissioning nucleus is presented. Variation of mass distribution with excitation energy and mass and charge of the fissioning nucleus is discussed. Qualitative explanation of the data has been sought in terms of existing theories of fission. The importance of charge and mass distribution studies in identifying the different reaction mechanisms in heavy ion induced reaction is highlighted.This article is dedicated to the memory of our beloved friend and colleague Dr. Tarun Datta who passed away on April 2, 1995.     

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%.     

Spectroscopic studies on crotonyl chloride and dimethyl acryl chloride

Infrared spectra of liquid samples of crotonyl chloride and dimethyl acryl chloride in the region 4000-600 cm⁻¹ have been recorded along with the Raman spectra in the region 4000-100 cm⁻¹. From CNDO/2 results and some band splitting, existence of conformers are inferred. A complete assignment of the spectra is made on the basis of reported spectral studies on related compounds and the relative variation of i.r. peak intensity with solvent polarity. Normal coordinate analysis of crotonyl chloride has been carried out for the first time.     

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%.     

Radiochemical extraction of mercury(II) from acidic chloride solutions using dialkylsulphides

The liquid-liquid extraction behavior of Hg(II) from aqueous acidic chloride solutions has been investigated by tracer techniques using dialkylsulphides (R₂S) namely, dibutylsulphide (DBS) and dioctylsulphide (DOS) as extractants. These extraction data have been analyzed by both graphical and theoretical methods by taking into account complexation of the metal ion in the aqueous phase with inorganic ligands and all plausible complexes extracted into the organic phase. The results clearly indicate that Hg(II) is extracted into xylene as HgCl₂ ^. nDBS/nDOS (where n = 2 and 3). The equilibrium constants of the extracted complexes have been deduced by non-linear regression analysis. The separation possibilities of Hg(II) from other metal ions viz. Ca(II), Mg(II), Ba(II) and Fe((III), which are present in the industrial wastes of the chlor-alkali industry has also been discussed.     

Radiochemical studies of the sorption behavior of strontium and barium

The sorption behavior of strontium and barium on kaolinite, bentonite and chlorite-illite mixed clay was studied by radioanalytical techniques using the batch method.⁹⁰Sr (29.1 y) and¹³³Ba (10.5 y) were used as radiotracers. Characterization of the solid matrices was done by FTIR and XRD spectrometries and specific surface area measurements. Synthetic groundwater was used as the aqueous phase. The variation of the distribution ratioR _d, as a function of metal ion loading was examined. The sorption isotherms were fitted to various isotherm models. The sorption energies were calculated to be in the range of 8–10 kJ/mol suggesting an ion exchange type of sorption mechanism. In detailed experiments, chlorite-illite mixed clay was first presaturated with K⁺, Sr²⁺, Ca²⁺ and Al³⁺ ions, respectively, prior to sorption studies with Ba²⁺ ions. The results of Ca²⁺ pretreated chlorite-illite were very similar to those of natural chlorite-illite, suggesting that the Ba²⁺ ion exchanges primarily with the Ca²⁺ ion on the clay minerals.