Preparation and characterization of an extraction chromatography column for technetium separation based on Aliquat-336 and silica gel support

An extraction chromatographic material based on Aliquat-336 anchored on hydrophobized silica gel support was prepared as an ion exchanger. The prepared material appeared to be suitable for the separation of ⁹⁹Tc from environmental matrices in column application. The properties of the material, sorption characteristic and distribution coefficient of ^99mTcO₄ ^-in various media were studied. The prepared sorbent was conditioned by washing with nitric acid. The solution containing ^99mTcO₄ ^- in 0.1M HNO₃ was passed through the column. Tc was eluted from the column by 8M HNO₃. The flow rate was 0.4 ml/min. The chemical yield of technetium during the separation process was determined using ^99mTc tracer and gamma measurement. The sorption recovery of Tc from the prepared sorbent with 0.1M HNO₃ solution was more than 98%, and the desorption recovery from the column using 8M HNO₃ varied between 92-96%. It was found that the prepared sorbent is suitable for the separation of technetium from environmental matrices and radioactive wastes. This revised version was published online in July 2006 with corrections to the Cover Date.     

Separation of Tc(VII) from Tc(IV) by solvent extraction

The solvent extraction of Tc(IV) and Tc(VII) by isoamyl alcohol has been studied. The TcCl ₆ ²⁻ and TcO ₄ ⁻ ions are both extracted from 3M H₂SO₄ solution but hydrolyzed Tc(IV) species are not. This permits the separation of the two valence states of technetium. The air oxidation of carrier-free hydrolyzed^99mTc(IV) may be limited by the presence of⁹⁹Tc carrier in the same chemical form. Paper chromatography and electrophoresis were used to identify TcCl ₆ ²⁻ , TcO ₄ ⁻ and hydrolyzed species. It was also found that the hydrolyzed ReCl ₆ ²⁻ can reduce TcO ₄ ⁻ to Tc(IV).     

Separation and purification of 99mTc from 99Mo produced by electron linear accelerator

The medical radionuclide ⁹⁹Mo was produced by the ¹⁰⁰Mo(γ,n) reaction using bremsstrahlung photons generated by an electron linear accelerator. The amount of ⁹⁹Mo produced was compared to that predicted by calculation using the particles and heavy ion transport code system. From the ⁹⁹Mo produced, highly pure ^99mTc was separated using the so-called technetium master milker, and the chemical yield of ^99mTc was 83–99 %. The installation of a new complex using this method and the electron linear accelerator with the preferable specification was suggested, and a possibility to supply the demand of ^99mTc was discussed and shown.

     

Studies on the porphine labeled with <Superscript>99m</Superscript>Tc–pertechnetate

The aim of this research is to use acetylacetonate as a ^99mTc chelating agent label with porphyrin and evaluate its radiochemical and biological characteristics. Stannous chloride was used as a reductant to determine the chemical and biological characterization of ^99mTc-complexes from labeling porphine{4′,4′′,4′′′-(2lH,23H-Porphine-5,10,15,20-terayl)tetrakis-(benzoic acid), TPPB} with ^99mTc–pertechnetate. Instant thin layer chromatography (ITLC), size exclusion chromatography (SEC), paper electrophoresis, and UV/Vis spectrophotometry were used to evaluate chemical characterization. Finally, biodistribution and liver function tests were applied to evaluate biological characteristics. The results of this study show that the labeling efficiency of ^99mTc(acac)–TPPB was nearly 100% when using acetylacetone (acac) as a conjugator. Three major ^99mTc(acac)–TPPB complexes were separated by SEC, and all of them were hydrophilic. The UV-Vis spectra of ^99mTc(acac)–TPPB complexes closely resembled those of the TPPB, but the wave lengths of their peaks changed 430, 521, 556, 591 and 647 nm after complexation. The biodistribution study selected the liver as the target organ. The ^99mTc(acac)–TPPB complex may cause short-term liver injury. However, this injury can be repaired, and the reagent is quickly metabolized. Hence, the toxicity of the ^99mTc(acac)–TPPB complex is within an acceptable range, and making it a promising liver imaging agent.     

Rapid and sensitive determination of pertechnetate in99Mo/99mTc generator eluates by reversed-phase high-performance liquid chromatography

Reversed-phase high-performance liquid chromatography with u.v. detection was applied for rapid and sensitive determination of pertechnetate in⁹⁹Mo/^99mTc generator eluates, using a mixture solvent of acetonitrile and 0.04M aqueous acetate buffer (1/1) containing a few volume percentage of 0.5 M tetra-n-butylammonium hydroxide as the mobile phase. Employing a -bondapak C₁₃ column, the TcO ₄ ^– species was separated, monitored with absorbance at 254 nm, and observed at the retention time of 3.5 min. The detection limit was found to be 5.2·10^–10 g of Tc for each injection. Total Tc contents in the^99mTc eluates from clinically-used⁹⁹Mo/^99mTc generator were analyzed by this technique. The^99mTc (⁹⁹Tc) species was separated from the contaminant⁹⁹Mo. This method was found to be useful for the purification of^99mTc (⁹⁹Tc) as well as the determination of total Tc content.     

Solvent extraction of reduced technetium from mineral acid solutions

The extraction of reduced^99mTc with 5,7-dichloroxine, tributyl phosphate (TBP) and 1-phenyl-3-methyl-4-benzoyl-pyrazolone-5 (PMBP) from HCl−LiCl mixtures has been studied. A mechanism of extraction is proposed and the stability of the chlorocomplexes of technetium (V) in a hydrochloric and—lithium chlorid—perchloric acid mixture has been established using extraction data of^99mTc and spectrophotometric measurements with⁹⁹Tc.     

Preparation and bioevaluation of <Superscript>99m</Superscript>Tc–carbonyl complex of guanine

The aim of this study is to prepare radiolabeled guanine with ^99mTc(CO)₃⁺ core. For this purpose, guanine has been radiolabeled with ^99mTc(CO)₃⁺ core. Quality control study of radiolabeled guanine molecule with ^99mTc(CO)₃⁺ core was performed by thin layer radio chromatography (TLRC) and high performance liquid radio chromatography (HPLRC). The results showed that the radiolabeling yield was quite high (94 ± 3%). Beside that ^99mTc(CO)₃–Gua complex has showed good in vitro stability during the 24 h period. Radiopharmaceutical potential of this complex was evaluated in Wistar Albino Rats. It was concluded that ^99mTc(CO)₃–Gua could be used as a nucleotide radiopharmaceutical for in vivo applications.     

Radiochenical determination of technetium-99 in LLW by chelation with sodium diethyl dithiocarbamate (NaDDC) and extraction with chloroform

A radiochemical method has been developed for the determination of⁹⁹Tc in low-level radioactive, waste from nuclear facilities, using^99mTc as an internal tracer. Radioactive contaminants were removed by carrier hydroxide precipitation and chelating extraction with NaDDC/CHCl₃ system at pH 4. The final technetium was chelated with NaDDC in 3N HCl solution and extracted selectively into chloroform. The average of radiochemical recovery for various types of LLW sample is about 90%. The decontamination factors for most radioactive nuclides are higher than 10⁵. The detection limit for⁹⁹Tc in a sample of about 10 g is 0.17 pCi/g (6.5 Bq·kg^–1) for a 100-minute count.     

Rapid estmation of technetium in99Mo−99mTc generators

A nomogram is presented to estimate the radiooctivity of^99mTc in⁹⁹Mo−^99mTc generators, based on equations of radioactive equilibrium. Since the parent element decays through two isomeric states of the daughter, the ratio of the total mass of technetium per millicurie of^99mTc is a function of the time elapsed between two consecutive elutions. Values of the amount of^99mTc expressed as a mole fraction or in moles or grams of total technetium per millicurie of^99mTc^m are also presented.     

Methyl ethyl ketone extraction of Tc species

Methyl ethyl ketone extraction of technetium species from aqueous solutions of neutron irradiated ammonium molybdate crystals was studied; the two species extracted were separated by high voltage paper electrophoresis. The one was the^99mTcO ₄ ^– ion and the other, a^99mTc non-charged immobile species, probably TcO₂.aq, which concentrated at the point of application on the electrophoresis paper strip.     

Determination of technetium-99 in environmental samples: A review

Due to the lack of a stable technetium isotope, and the high mobility and long half-life, ⁹⁹Tc is considered to be one of the most important radionuclides in safety assessment of environmental radioactivity as well as nuclear waste management. ⁹⁹Tc is also an important tracer for oceanographic research due to the high technetium solubility in seawater as TcO₄⁻. A number of analytical methods, using chemical separation combined with radiometric and mass spectrometric measurement techniques, have been developed over the past decades for determination of ⁹⁹Tc in different environmental samples. This article summarizes and compares recently reported chemical separation procedures and measurement methods for determination of ⁹⁹Tc. Due to the extremely low concentration of ⁹⁹Tc in environmental samples, the sample preparation, pre-concentration, chemical separation and purification for removal of the interferences for detection of ⁹⁹Tc are the most important issues governing the accurate determination of ⁹⁹Tc. These aspects are discussed in detail in this article. Meanwhile, the different measurement techniques for ⁹⁹Tc are also compared with respect to advantages and drawbacks. Novel automated analytical methods for rapid determination of ⁹⁹Tc using solid extraction or ion exchange chromatography for separation of ⁹⁹Tc, employing flow injection or sequential injection approaches are also discussed.     

Preparation and biodistribution of99mTc-HT18

The preparation of N₁-(octadecylcarbomyl-methy)-ethylenediaminetriacetic acid labelled with^99mTc is described. Reduction of technetium was made using sodium borohydride (procedure A) or stannous chloride (procedure B), and the labelling efficiency was checked by thin layer chromatography. Preliminary studies of biol-behavior of this complex were performed in white rats.     

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 ^– .     

Radiochemical determination of technetium-99

The radiochemistry of technetium-99 is reviewed and the different measurement techniques are compared. Experimental results on sorption of technetium on two different types of ion exchange resins using^99mTc and^95mTc as chemical yield tracers are presented. Spectra calibrations of liquid scintillation counter using^95mTc as chemical yield tracer of⁹⁹Tc are discussed.     

Preparation of technetium-99m-humic complex by ligand exchange from hexakis (thiourea-S)technetium(III) complex

The preparation of technetium-99m-humic complex without presence of any metal reductant was studied. For the preparation of Tc-HA complex by ligand substitution hexakis(thiourea-S)technetium(III) complex was used as a precursor. Ligand exchanging reaction was studied with two different humate/thiourea concentration ratios. After mixing of [^99mTc(tu)₆]³⁺ complex with natrium humate under a nitrogen atmosphere a formation of technetium humate wasobserved. The determination of reaction products was performed by combination of gel and paper chromatography. Reaction yields are dependent on humate/thiourea concentration ratio and reaction time. Tc-HA complex was obtained with the highest yield of 62%. Reaction mixture also contains a technetium dioxide as a side product of exchanging reaction and other technetium species, which are also discussed. Oxidation state of technetium in prepared Tc-HA complex is apparently unchanged.     

Bioevaluation of 99mTc(CO)3–Guanine in vitro and in vivo

The aim of this study is to examine biological behaviour of radiolabeled guanine with [Tc(CO)₃]⁺ core in vitro and in vivo. In vitro biological behavior of ^99mTc(CO)₃–Gua was evaluated on Lung (A-549), Breast (MCF-7), Colonic (Caco) carcinoma cell lines and normal human bronchial epithelial (NHBE). ^99mTc(CO)₃–Gua compound showed high uptake on A-549 cell line when compared to NHBE cell line. Biodistribution characteristics of ^99mTc(CO)₃–Gua was evaluated using New Zeland Rabbits. Scintigraphic results showed that a high level of radioactivity was observed in the lungs and liver shortly after administration of the ^99mTc(CO)₃–Gua and excretion takes place via both renal and hepatobiliary route. It was concluded that ^99mTc(CO)₃–Gua could be used as a nucleotide radiopharmaceutical for imaging purposes.     

Exchange labeling of proteins:99mTc labeled transferrin

^99mTc-labeled transferrin was prepared by reduction of^99mTcO ₄ ⁻ ; with stannous DTPA or stannous citrate followed by equilibration of the technetium chelate with human transferrin. The rate of transfer of^99mTc to transferrin in the presence of 0.015M citrate buffer was dependent on pH in the order pH 2.1> pH 7.2> pH 4.1> pH 5.9. The incorporation rate was inversely proportional to the concentration of DTPA and citrate buffer. The replacement of citrate buffer by acetate buffer or oxalate buffer reduced drastically the formation of^99mTc-labeled transferrin at pH 4.1. The formation of^99mTc-labeled transferrin prepared from the reduction of^99mTcO ₄ ⁻ with stannous citrate was faster than that from the reduction with stannous DTPA in the presence of 0.015M citrate buffer and pH 2.5. Equilibration of transferrin with^99mTc-labeled pyrophosphate did not produce^99mTc-labeled transferrin at pH 4.5. The ligand exchange labeling of^99mTc to transferrin in 0.015M citrate did not cause appreciable denaturation of the protein at all pH values. This method also enabled labeling of the protein in a low concentration (2.6·10⁻⁴ M) via tin reduction. Sequential external imaging of the^99mTc-labeled transferrin in Sprague-Dawley rats bearing Walker-256 carcinosarcoma showed optimal tumor localization occurred at 3 hr after injection. In spite of this,^99mTc-labeled transferrin does not appear to be a suitable imaging agent because of the low tumor to blood ratio of^99mTc (0.50±0.17) at 3 hr post injection. This is similar to that of^{6 7}Ga-citrate (0.43±0.15%).     

Systematic radiochemical separation for the determination of <Superscript>99</Superscript>Tc, <Superscript>90</Superscript>Sr, <Superscript>94</Superscript>Nb, <Superscript>55</Superscript>Fe and <Superscript>59,63</Superscript>Ni in low and intermediate radioactive waste samples

A simple and rapid separation procedure was systemized for the determination of ⁹⁹Tc, ⁹⁰Sr, ⁹⁴Nb, ⁵⁵Fe and ^59,63Ni in low and intermediate level radioactive wastes. The integrated procedure involves precipitation, anion exchange and extraction chromatography for the separation and purification of individual radionuclide from sample matrix elements and from other radionuclides. After separating Re (as a surrogate of ⁹⁹Tc) on an anion change resin column, Sr, Nb, Fe and Ni were sequentially separated as follows; Sr was separated as Sr (Ca-oxalate) co-precipitates from Nb, Fe and Ni followed by purification using Sr-Spec extraction chromatographic resin. Nb was separated from Fe and Ni by anion exchange chromatography. Fe was separated from Ni by anion exchange chromatography. Ni was separated as Ni-dimethylglyoxime precipitates after the removal of ^134,137Cs and ^110mAg by Cs-phosphotungstate and AgCl precipitation, respectively. Finally, the radionuclide sources were prepared by precipitation for their radioactivity measurements. The reliability of the procedure was evaluated by measuring the recovery of chemical carriers added to a synthetic radioactive waste solution.     

Synthesis and biodistribution of two novel 99mTc “3+1”mixed ligand complexes as potential brain perfusion agents

The research in the last decade has been mainly aimed at the development of technetium-99m radiopharmaceuticals, among which are the “3+1”mixed ligand complexes. Two novel [^99mTc]“3+1”mixed ligand complexes each carrying the tridentate ligand, the N-(o-Methylthiophenyl)ethylenediamine or the N-(o-Methylthiophenyl)-b-mercaptoacetamide in combination with monothiolate coligand were produced using stannous chloride as reductant and glucoheptonate as transfer ligand. The identification of [^99mTc]-6 and [^99mTc]-7 was established by thin layer chromatography. The radiochemical purity of two complexes was over 90%. Biodistribution data in mice showed that both [^99mTc]-6 and [^99mTc]-7 can penetrate the intact blood-brain barrier and exhibited retention in mice brain. The brain uptakes (%ID/g) were 1.76, 1.17, 0.90 and 0.68, 0.38 ,0.37 at 2, 30, and 60 minutes i.v. postinjection for [^99mTc]-6 and [^99mTc]-7, respectively. Examples in this report comfirm us that it is promising to develop ^99mTc complexes as potential brain perfusion agents based on modifying either the tridentate or the monodentate ligands. This revised version was published online in August 2006 with corrections to the Cover Date.     

The interaction of <Superscript>99m</Superscript>Tc with pyrimidine compounds

The reaction of ^99mTc of different oxidation states (+7, +4) with 2-thiouracil and 5-nitrobarbituric acid have been studied at different temperatures, pH and concentrations. The reaction mixtures have been analyzed at different times using thin layer chromatography (TLC) and a radio detector to show the peaks at the plates. ^99mTc is obtained from the Mo generators with oxidation state (+7). The use of SnCl₂ as a reducing agent gave ^99mTc with oxidation state (+4). It is very difficult to separate the complexes formed from the reactions in very small concentration. The percentage of ^99mTc and its oxidation state involved in the complexes can be determined. The labeling efficiencies (percentage of complex) in the reaction of ^99mTc⁺⁷ with 5-nitro-barbituric-acid increases mostly at pH  10. Both oxidation states of ^99mTc(+7, +4) can be detected at pH’s 4 and 10, but at pH  4, the reduced form ^99mTCO₂, is more pronounced. At pH  7 no complexes were detected and most of ^99mTc remains as ^99mTCO₄ ⁻ . By increasing the ligand concentration, the labeling efficiencies of the complex increases. For the reaction of ^99mTc of oxidation states (+4, +7) with 2-thiouracil at different temperatures and analytical times it is concluded that several complexes with different R_f values were observed in equilibrium and most of these complexes were unstable.