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.     

Separation of no-carrier-added As and Se produced in 16O irradiated cobalt target

No-carrier-added radionuclides of arsenic and selenium were produced in ¹⁶O irradiated cobalt target matrix. The initial products, formed by ⁵⁹Co(¹⁶O,xn)^70-73Br reaction, decayed promptly to arsenic and selenium radionuclides, which were subsequently separated by liquid-liquid extraction (LLX) using di-(2-ethylhexyl) phosphoric acid (HDEHP) and trioctylamine (TOA) as liquid ion exchangers.     

Separation of no-carrier-added radioactive scandium from neutron irradiated titanium

In this work, sorption of Ni(II) from aqueous solution to goethite as a function of various water quality parameters and temperature was investigated. The results indicated that the pseudo-second-order rate equation fitted the kinetic sorption well. The sorption of Ni(II) to goethite was strongly dependent on pH and ionic strength. A positive effect of HA/FA on Ni(II) sorption was found at pH < 8.0, whereas a negative effect was observed at pH > 8.0. The Langmuir, Freundlich, and D-R models were applied to simulate the sorption isotherms at three different temperatures of 293.15 K, 313.15 K and 333.15 K. The thermodynamic parameters (ΔH ⁰, ΔS ⁰ and ΔG ⁰) were calculated from the temperature dependent sorption, and the results indicated that the sorption was endothermic and spontaneous. At low pH, the sorption of Ni(II) was dominated by outer-sphere surface complexation or ion exchange with Na⁺/H⁺ on goethite surfaces, whereas inner-sphere surface complexation was the main sorption mechanism at high pH.     

Separation of nca 123,124,125,126I from alpha particle induced the natural antimony trioxide target

Natural Sb₂O₃ target was irradiated with 29.4 MeV α beam to produce no-carrier-added (nca) ^{123,124,125,126}I radionuclides. Attempt has been made to separate nca iodine from bulk antimony oxide by solvent extraction using CCl₄, solid–liquid extraction using Dowex 1 as anion exchanger, and by precipitation methods using different precipitating agents like HCl, AgNO₃, Na₂S and Zn powder. Only the solvent extraction method was found suitable for separation of nca iodine from bulk antimony target.     

Simultaneous production and separation of no-carrier-added 111In, 109Cd from alpha particle induced silver target

A natural silver foil was bombarded by 30 MeV α-particles which produced ¹¹¹In, ¹⁰⁹Cd and ^106mAg in the target matrix. ¹¹¹In and ¹⁰⁹Cd were separated from the Ag target matrix employing ion-exchange chromatography and liquid–liquid extraction (LLX). In the chromatographic separation, the active solution containing the NCA products were adsorbed in the column containing Dowex 50 and were eluted with HNO₃. Bulk silver and ¹⁰⁹Cd were sequentially eluted with 1 M HNO₃. After complete elution of ¹⁰⁹Cd and the bulk, ¹¹¹In was eluted with 1.5 M HNO₃. In the LLX, the NCA ¹¹¹In was extracted to 1 % HDEHP (di-2(ethylhexyl)phosphoric acid) from 10^?2 M HNO₃ solution, leaving cadmium and bulk silver quantitatively in the aqueous phase. The NCA ¹⁰⁹Cd was separated from the bulk Ag by precipitating Ag as AgCl. NCA ¹¹¹In was stripped back quantitatively from HDEHP phase using 8 M HNO₃.     

Separation of carrier-free lutetium-177 from neutron irradiated natural ytterbium target

Neutron irradiation of naturally occurring Yb produces small amounts of carrier-free¹⁷⁷Lu activity. Cation exchange chromatography in the displacement development mode using Dowex-50X8, 200–400 mesh resin, and Zn²⁺ as the separating ion was used to separate¹⁷⁷Lu produced in a neutron irradiated Yb target. 0.04M -hydroxyisobutyric acid at pH 4.6±2 and temperature 26±1°C was used to elute carrier-free¹⁷⁷Lu in 70% yield and at a radionuclidic purity greater than 99%.     

Separation of no-carrier-added 109Cd from natural silver target using RTIL 1-butyl-3-methylimidazolium hexafluorophosphate

The room temperature ionic liquid (RTIL), 1-butyl-3-methylimidazolium hexafluorophosphate [C₄mim][PF₆] has various applications in the separation of a range of metal ions replacing volatile and toxic traditional organic solvents in liquid–liquid extraction systems. In this study, the RTIL [C₄mim][PF₆] was used to separate no-carrier-added (NCA) ¹⁰⁹Cd from α-particle irradiated Ag target. A natural Ag foil was bombarded by 30 MeV α-particles to produce ¹⁰⁹Cd. After the decay of all co-produced short-lived products, NCA ¹⁰⁹Cd was separated from the bulk Ag using [C₄mim][PF₆] as extractant from HNO₃ medium. Ammoniumpyrrolidine dithiocarbamate (APDC) was used as a complexing agent. At the optimum condition, 3 M HNO₃, 0.01 M APDC in presence of [C₄mim][PF₆], ~99 % bulk Ag was extracted to the IL phase, leaving NCA ¹⁰⁹Cd in the aqueous phase. The amount of Ag became negligibly small after re-extraction in the same condition. The ionic liquid was recovered by washing it with 1 M HCl.     

Production and separation of no-carrier-added 48V from 16O irradiated chlorine target

The viability of ground coal bottom ash as a potential Portland cement constituent to be used in building materials is assessed. Currently, coal fly ash is used to produce Portland cements and concretes. However, coal bottom ash is mainly landfilled. Gamma spectrometry analysis, compressive strength, physical and chemical testing were performed. The ground coal bottom ash activity concentration index (I = 1.03) was compared to that of the coal fly ash (I = 1.11) provided from the same thermo-electrical power plant. Ground coal bottom ash could be used in building materials in the same way as coal fly ash as a Portland cement constituent.

     

Solvent extraction of no-carrier-added 103Pd from irradiated rhodium target with a-furyldioxime

Summary Solvent extraction of no-carrier-added ¹⁰³Pd was investigated from irradiated rhodium target with a-furyldioxime in chloroform from diluted hydrochloric acid. Extraction yield was 85.3% for a single extraction from 0.37M HCl and ¹⁰³Pd purity was better than 99%.     

Separation of no-carrier-added <Superscript>90</Superscript>Nb from proton induced natural zirconium target

Amongst various radionuclides of molybdenum, ⁹⁰Mo and ⁹⁹Mo have suitable β energy for clinical uses. In this paper we report separation of ⁹⁹Mo from ⁹⁹Mo-^99mTc equilibrium mixture. The liquid–liquid extraction technique has been employed using trioctylamine (TOA) diluted in cyclohexane as organic phase and HCl as aqueous phase. At 10⁻⁵ M HCl and 0.5 M TOA concentration ^99mTc quantitatively transferred to the organic phase leaving ⁹⁹Mo in the aqueous phase. The developed separation method is efficient and provides very high separation factor.     

Wet harvesting of no-carrier-added 211At from an irradiated 209Bi target for radiopharmaceutical applications

Astatine-211 is one of the most promising -emitters for targeted cancer radiotherapy. However, research and clinical trials involving ²¹¹At-labeled radiopharmaceuticals have often been impeded due to the irregular and sometimes inconveniently low recovery yields obtained by the currently used dry distillation procedure. Therefore, a wet harvesting procedure isolating ²¹¹At from an irradiated ²⁰⁹Bi target was explored. The procedure involves target dissolution in concentrated HNO₃ and extraction of the high oxidation state ²¹¹At activity with butyl or isopropyl ether. This method resulted in consistent and nearly quantitative yields. The activity was re-extracted in aqueous phase and applied to NIS6 UVW human glioma cells transfected with cDNA encoding the human sodium/iodide symporter (NIS). The significant and specific uptake of ²¹¹At activity by these cells suggests that in the ether phase, high oxidation state ²¹¹At is reduced to [²¹¹At]astatide anion. The synthesis of the first astatinated organic compound derived from wet harvested ²¹¹At, 3-astatobenzoic acid (ABA), was achieved.This work was supported by Grants EB002980, CA42324 and CA91927 from the U.S. National Institutes of Health. Special thanks go to Michael Dailey and Shawn Murphy from the Duke University Medical Center PET Cyclotron Department for providing us with ²¹¹At activities and to Kevin Alston for the preparation of the bismuth targets. NIS cDNA was kindly gifted by Dr. Sissy M. Jhiang from Ohio State University, Columbus, Ohio.     

Wet harvesting of no-carrier-added 211At from an irradiated 209Bi target for radiopharmaceutical applications

Astatine-211 is one of the most promising -emitters for targeted cancer radiotherapy. However, research and clinical trials involving ²¹¹At-labeled radiopharmaceuticals have often been impeded due to the irregular and sometimes inconveniently low recovery yields obtained by the currently used dry distillation procedure. Therefore, a wet harvesting procedure isolating ²¹¹At from an irradiated ²⁰⁹Bi target was explored. The procedure involves target dissolution in concentrated HNO₃ and extraction of the high oxidation state ²¹¹At activity with butyl or isopropyl ether. This method resulted in consistent and nearly quantitative yields. The activity was re-extracted in aqueous phase and applied to NIS6 UVW human glioma cells transfected with cDNA encoding the human sodium/iodide symporter (NIS). The significant and specific uptake of ²¹¹At activity by these cells suggests that in the ether phase, high oxidation state ²¹¹At is reduced to [²¹¹At]astatide anion. The synthesis of the first astatinated organic compound derived from wet harvested ²¹¹At, 3-astatobenzoic acid (ABA), was achieved.This work was supported by Grants EB002980, CA42324 and CA91927 from the U.S. National Institutes of Health. Special thanks go to Michael Dailey and Shawn Murphy from the Duke University Medical Center PET Cyclotron Department for providing us with ²¹¹At activities and to Kevin Alston for the preparation of the bismuth targets. NIS cDNA was kindly gifted by Dr. Sissy M. Jhiang from Ohio State University, Columbus, Ohio.     

Production of 119mSn by alpha particle bombardment of 116Cd and its carrier-free separation

The production method of high specific ^119mSn was studied by using the reaction of alpha particles with enriched cadmium. The excitation function for the ¹¹⁶Cd(α, n) ^119mSn reaction and its thick-target yields were investigated with the stacked foil technique at the incident alpha particle energy of 25 MeV. When the incident alpha particle energy of 20 MeV was chosen, 0.1 μCi/μA·h of ^119mSn could be produced at the end of bombardment. The procedure for the carrier-free separation of tin activity from the cadmium target and the copper backing by coprecipitation, organic solvent extraction and anion exchange is described.     

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.     

Wet-chemistry method for the separation of no-carrier-added 211At/211gPo from 209Bi target irradiated by alpha-beam in cyclotron

We present a fast and effective wet-chemistry method, used to obtain the pure alpha-emitter ²¹¹At/^211gPo (T _1/2 = 7.214 h/516 ms), produced by ²⁰⁹Bi(α,2n) reaction in NCA form. It is a selective radiochemical separation of the At radionuclides from the target and the impurities, characterized by a radionuclidic purity close to 100%, based on the dissolution and the dilution of the irradiated target in acidic medium, on the extraction with DIPE, followed by the back-extraction with NaOH. As a result, we obtain a yield greater than 90–97% in a range from 0.75M to 2.00M.