Solvent extraction of99mTc/VII/ with methylene blue into nitrobenzene

The extraction of^99mtechnetium/VII/ with methylene blue into organic solvent has been investigated. Nitrobenzene, which was found to be the most effective extractant for^99mTc/VII/, was used to separate^99mTc/VII/ from other elements. The effect of various parameters on the extraction coefficient value such as effect of pH, time of equilibration, effect of anions and cations on the E value have been evaluated. The stoichiometry of metal to reagent was determined by the slope ratio method and was found to be 11.     

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.     

Desorption of99Mo from spent99Mo/99mTc generator

A simple method for desorption and purification of⁹⁹Mo from spent⁹⁹Mo/^99mTc generators is described. The alumina column was washed successively with 0.9% saline water, 35% H₂O₂, and then the⁹⁹Mo was eluted with 2M NH₄OH. Ammonia and residual H₂O₂ were removed by heating the eluate. Finally,⁹⁹Mo solution was passed through a 0.2 m membrane filter to remove precipitated aluminium hydroxide.     

Pharmaceutical grade sodium [99mTc] pertechnetate from low specific activity 99Mo using an automated 99Mo/99mTc-TCM-autosolex generator

Performance study of a computer controlled automated closed cyclic module for the separation and recovery of ^99mTc from low specific activity (n, γ) ⁹⁹Mo using methyl ethyl ketone (MEK) solvent extraction technique named ⁹⁹Mo/^99mTc-TCM-AUTOSOLEX (Technetium automated solvent extraction) Generator is described. The entire system is automated and controlled by a user-friendly PC based graphical user interface that actually supervises process via an embedded system based electronic controller. The average yield of separation of ^99mTc was above 85 % and ⁹⁹Mo breakthrough in ^99mTc pertechnetate was <0.002 %. The sodium pertechnetate obtained was a clear solution having pH 6–7, Radiochemical (RC). Purity >99 %, MEK content <0.1 % (v/v), Al and Mo content <10 µg/ml. R. C. Purity of ^99mTc-radiopharmaceuticals studied was not less than 96 %. Bio-Quality control studies confirm that sodium pertechnetate obtained was sterile and pyrogen free. Imaging studies in animals and humans with limited radiopharmaceuticals show that the quality of ^99mTc-pertechenate obtained in the present module was good enough to do clinical study.     

Solvent extraction of In/III/ with 1,2,3-bezotriazole into n-heptanol

Aqueous 1,2,3-benzotriazole has been used for the extraction of In/III/ in alkaline medium. The extraction of In/III/ was found to be better than 99% over the pH range 5.0–10.0 and an equilibration time of 2.0 min. The effect of anions and cations on the extraction coefficient has been studied. The stoichiometry of metal: reagent determined by the slope-ratio method was found to be 13. Separation factors for around 20 elements were better than 10³.     

Chemical effects of (n, γ) nuclear reaction on (Mo6Cl8)Cl4

The chemical effects of⁹⁸Mo(n, )⁹⁹ Mo reaction on molybdenum(II) chloride [(Mo₆Cl₈)Cl₄] have been studied. Retention, thermal and radiolytical annealing were determined. It was found that this molybdenum compound has low retention, a negligible tendency to thermal annealing and a virtual insensitivity to hydrolysis. For practical application in the enrichment of⁹⁹Mo by the Shilard-Chalmers method, molybdenum(II) chloride [(Mo₆Cl₈)Cl₄] appears to offer good prospects.     

A study on the solvent extraction of Ag/I/ with 1,2,3-benzotriazole in chloroform

A rapid and selective method has been developed for the substoichiometric extraction of Ag/I/with 1,2,3-benzotriazole /1,2,3-BT/ in chloroform in the presence of versenate. The effect of various parameters such as pH, time of equilibration, solvent, anions, cations, etc., on the extraction coefficient value has been studied. The stoichiometry of the extracted species of 11 /Ag:1,2, 3-BT/ was obtained by the slope ratio method and substoichiometric extraction. Decontamination factors for most elements in the substoichiometric extraction of Ag/I/ were found to be higher than 10⁴.     

The quality of99mTc eluates

The possible effects of several protecting procedures on the quality of^99mTc eluates were investigated. The content of⁹⁹Mo in the eluates (⁹⁹Mo breakthrough) was expressed in (%) with respect to the total adsorbed⁹⁹Mo radioactivity and in () i.e. as the ratio of⁹⁹Mo and^99mTc radioactivities in each particular eluate. The radiochemical purity was expressed in (%) of^99mTc(VII) in the eluates. The content of Al³⁺ and Cu²⁺ as chemical impurities was also determined.     

Evaluation of proton induced reactions on 100Mo: New cross sections for production of 99 mTc and 99Mo

The use of the ⁹⁹Mo^99mTc generator in nuclear medicine is well established world wide. The production of the ⁹⁹Mo (T_1/2 = 66 h) parent as a fission product of ²³⁵U is largely based on the use of reactor technology. From the early 1990's accelerator based production methods to provide either direct produced ^99mTc or the parent ⁹⁹Mo, were studied and suggested as potential alternatives to the reactor based production of ⁹⁹Mo. A possible pathway for the charged particle production of ^99mTc and ⁹⁹Mo is irradiation of molybdenum metal with protons via the reaction ¹⁰⁰Mo(p,2n)^99mTc and ¹⁰⁰Mo(p,pn)⁹⁹Mo, respectively. The earlier published excitation functions show large differences in their maximum that result in large differences in the calculated yields. We therefore decided to study the excitation function for these proton-induced reactions. In this work the newly measured excitation functions as well as an evaluation of earlier measured data and a discussion of the observed disagreements are presented.     

Solvent extraction of Fe/III/ with 1,2,3-benzotriazole into n-heptanol

A new and rapid method has been developed for the quantitative extraction of Fe/III/ with 1,2,3-benzotriazole /1,2,3-BT/ into n-heptanol. The extaction coefficient value of Fe/III/ between n-heptanol and an aqueous 1% solution of 1,2,3-BT was found to be better than 99% over the pH range of 7.3 to 8.0 for an equilibration time of 2.0 min. The effect of various other parameters on the extraction coefficient value of Fe/III/ such as solvents, anions and cations etc. has also been studied. The stoichiometry of the metal: reagent determined by the method of substoichiometric extraction and slope-ratio method was found to be 13. Separation factors for most of the elements studied were better than 10³.     

Neptunium distribution in a high acid first cycle Purex Process

This work deals with the extraction behavior of neptunium in a high acid Purex Process. The composition of PWR fuel type with 3.2% enrichment, 500 MWd/t burn-up and 100 d cooling time was considered. Two consecutive cold runs were performed in a mock-up facility at IPEN-CNEN/SP with simulated feed solutions containing: 3M HNO₃; 1M U; 455 g²³⁷Np labeled with²³⁹Np; 15 mg Zr l^–1, 12 mg Ce l^–1, 7 mg Ru l^–1 and 13 mg Mo l^–1 traced with active isotopes⁹⁵Zr,¹⁴¹Ce,¹⁰³Ru and⁹⁹Mo as FP. A 30 vol% TBP/n-dodecane was used as solvent. Countercurrent experiments were carried out using two 16 stages plexiglass mixer-settlers, at 25°C, during 21 h continuous operation, with O/A ratio of 2 in the extraction section and 9 and 13 in the 1st and 2nd scrubbing sections, respectively. For a 65% organic loading, ca. 77% of neptunium remains in the waste stream, without any Np valence adjustment.     

Separation of technetium(VII) from irradiated MoO3 sample by solvent extraction with tri-iso-octylamine

Summary A solvent extraction method for the separation of technethim and molybdenum is outlined. After irradiation of MoO₃ and dissolution in sodium hydroxide, the short-lived ^99mTc isotope is extracted from 1 M hydrochloric acid into a solution of tri-iso-octylamirie in 1,2-dichloroethane. The percentage of ⁹⁹Mo in organic phase is less than 0.5%.

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Zusammenfassung Eine Extraktionsmethode zur Trennung von Technetium und Molybdän wird beschrieben. Hierbei wird nach Neutronenbestrahlung von MoO₃ und Auflösung in Natronlauge das kurzlebige ^99mTc-Isotop aus 1 m salzsaurer Lösung in eine Tri-iso-octylaminlösung in 1,2-Dichloräthan extrahiert. Weniger als 0,5% ⁹⁹Mo finden sich in der organischen Phase.

     

Solvent extraction of cerium/III/ with 1-/2-pyridylazo/-2-naphthol from perchloric acid media

A study on solvent extraction of cerium/III/ ion with 1-/2-pyridylazo/-2-naphthol /PAN or HL/ in chloroform from perchloric acid solution is described. The effect of equilibrium time, the pH of the aqueous phase and the concentration centration of extractant in organic phase on the extraction efficiency of cerium/III/ has been studied. The results show that the mechanism of extraction reaction is 3Ce _/aq/ ³⁺ + 3HL_/o/ CeL_3/o/ + 3H ₊ ^/aq/     

Chemical and radiochemical evaluation of the purity of99mTc extracted by MEK

Solvent extraction separation of^99mTc from⁹⁹Mo using methyl ethyl ketone(MEK) has been found to be an effective method of obtaining^99mTc of medicinal purity from low specific activity⁹⁹Mo. The authors have investigated the effect of alkali and molybdenum concentration on the extraction of⁹⁹Mo and^99mTc into methyl ethyl ketone. The possibility of methyl ethyl ketone forming enol and condensation products and its effect on the final extraction efficiency and purity of^99mTc has been studied. Sodium molybdate has been found to have a good salting out effect on^99mTc pertechnetate and hence^99mTc extraction can be better accomplished from low specific activity⁹⁹Mo solutions. The ketone seems to form traces of condensation products in the extraction procedure. These have been found to be coextracted with^99mTc into MEK but did not affect the extractability of^99mTc. It was observed that neutral alumina column removes these condensation products from MEK containing^99mTc. Alternately these could be filtered off by acidification of the final aqueous^99mTc solution. The studies indicate that under optimum experimental conditions methyl ethyl ketone separates^99mTc from⁹⁹Mo with high efficiency and yields^99mTc of high purity suitable for use in nuclear medicine in the form of various labelled compounds.     

The application of radioactive isotope99Mo to the reconstituted MoFe protein

By substututing⁹⁹Mo for the Mo in the reconstituted MoFe protein, the nuclear quadrupole interactions (NQI) of⁹⁹Mo have been measured using the perturbed angular correlations (PAC). Two well-defined electric quadrupole interaction parameters have been observed. The configuration of the M-Center of the MoFe protein is identified by the quadrupole couplign constant _Q1(412(9)MHz) and the asymmetry parameter ₁(0.49(5)). Other parameters, V_Q2(1939(13)MHz) and ₁(0.90(1)), may correspond to a deformation M—Center of MoFe protein.     

A simple and sensitive separation technique of 99Mo and 99mTc from their equilibrium mixture

The present work describes a simple and inexpensive separation method of ⁹⁹Mo from the equilibrium mixture. The liquid–liquid extraction technique has been employed to separate ⁹⁹Mo and ^99mTc using triisooctylamine (TIOA). The ⁹⁹Mo and ^99mTc were quantitatively separated out in 2 M TIOA with tripled distilled water; ^99mTc was back extracted from TIOA organic phase to aqueous phase by 0.1 M DTPA. The species information or indirect speciation of molybdenum was also established by the extraction profile of the molybdenum.     

Determination of Np,Pu and Am in high level radioactive waste with extraction-liquid scintillation counting

A new method for the determination of transuranium elements, Np, Pu and Am with extraction-liquid scintillation counting has been studied systematically. Procedures for the separation of Pu and Am by HDEHP-TRPO extraction and for the separation of Np by TTA-TiOA extraction have been developed, by which the recovery of Np, Pu and Am is 97%, 99% and 99%, respectively, and the decontamination factors for the major fission products (⁹⁰Sr,¹³⁷Cs etc.) are 10⁴–10⁶. Pulse shape discrimination (PSD) technique has been introduced to liquid scintillation counting, by which the counting efficiency of -activity is >99% and the rejection of -counts is >99.95%. This new method, combining extraction and pulse shape discrimination with liquid scintillation technique, has been successfully applied to the assay of Np, Pu and Am in high level radioactive waste.     

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.     

Organic Synthesis and Technetium-99m Labeling of Some Amino-Phenol Ligands

We reported the synthesis and labeling of one tetradentate and two pentadentate amino-phenol ligands with technetium-99m by the direct pertechnetate addition and by ligand exchange methods. Labeling by direct pertechnetate addition was attended by adding pertechnetate eluate to the ethanolic solution of the amino-phenol ligands at pH 9. Stannous chloride dihydrate was used as reducing agent. Exchange studies were carried out via the use of the following ^99mTc-chelates: ^99mTc-DTPA, ^99mTc-gluconate, ^99mTc-tartrate and ^99mTc-citrate complexes. Ligand exchange method was achieved by incubation the ligand solutions with ^99mTc-co-ligands complexes in 0.05M bicarbonate buffer pH 9. At this pH value the ^99mTc-co-ligands dissociated and the more stable new ^99mTc-ligands were formed with high radiochemical yield 95%. The radiochemical yield of ^99mTc-labeled amino-phenol ligands were estimated by solvent extraction, electrophoresis and HPLC methods. The produced technetium-99m amino-phenol complexes were neutral, lipophilic and stable during the period of 24 hours.     

Determination of99Tc in coastal seawater collected in Fukuoka,Japan

Concentrations of⁹⁹Tc were determined by inductively coupled plasma mass spectrometry (ICP-MS) on coastal seawater in the general environment in Japan. Technetium was enriched on iron hydroxide by repetitive co-precipitation method from a large volume of seawater and separated from impurities by solvent extraction and ion-exchange techniques. The concentrations of⁹⁹Tc were 1.0 to 7.4 Bq1^–1, which was one order of magnitude lower than the level reported on seawater from general environment by beta-ray counting. Concentrations of¹³⁷Cs determined on the same seawater were 3.7 and 3.9 mBq1^–1. The activity ratio of⁹⁹Tc/¹³⁷Cs was calculated to be 2.7×10^–4. This ratio was very close to the value expected for fallout from nuclear tests.