In vivo and in vitro 99mTc-protein bound of renal agents: 99mTc-prylidinomethyltetracycline (99mTc-Sn-Pmt) and 99mTc-Sn-Gluco-ene-diolate (99mTc-Gluco)

Protein binding affects tissue distribution, plasma clearance and uptake of renal radiopharmaceuticals. The ^99mTc bound to plasma protein after incubation ^99mTc-Gluco-ene-diolate (^99mTc-Sn-Gluco) agent or ^99mTc-prylidinomethyl-tetracycline (^99mTc-Sn-PMT) agent with plasma protein. It was observed that the protein bound to ^99mTc is lesser extent with (^99mTc-Sn-Gluco) agent than with the ^99mTc-PMT agent. ^99mTc-Sn-PMT is excreted more rapidly than ^99mTc-Sn-Gluco. On the other hand the percentage binding to protein seems to depend on the origin of the protein and or the type of protein (human or animal). However lower human protein binding or higher protein binding were observed with ^99mTc-Sn-Gluco or with ^99mTc-Sn-PMT, respectively compared with the binding to rat protein. The unbroken down of the chemical form of the origin of these two agents and the highest of ^99mTc-Sn-Gluco remained as origin in urine indicate that ^99mTc-Sn-Gluco are more stable than ^99mTc-Sn-PMT.Concerning the type of protein binding to ^99mTc-Sn-PMT or to ^99mTc-Sn-Gluco, it was observed that Human Plasma Protein is greater binding than Human serum protein or than IgG.     

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.     

Technetium-99 in “instant”99mTc-pertechnetate

The⁹⁹Tc-content in^99mTc-pertechnetate separated from⁹⁹Mo by distillation or extraction has been studied with a plastic scintillation detector. The identification of the measured activity was achieved by beta-spectrometry, chemical separation and half-life studies. The frequency distribution of the⁹⁹Tc/^99mTc-ratios in the different samples was observed to be log-normal. The most likely activity ratio was 0.4·10⁻⁶, the maximum value being 5·10⁻⁶. The specific activity of “instant” pertechnetate is approximately a factor of 60 lower than that normally recorded in pertechnetate derived from daily eluted column generators. The low specific activity of “instant” pertechnetate is primarily explained by the long time between separation and usage and secondly by the low yield of Tc in the distillation and extraction processes. In several of the “instant” pertechnetate solutions the carrier concentration exceeded the reductive capacity of the stannous ions in “kits” with small amounts of Sn(II) in usable form.     

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.     

A99Mo-99mTc generator based on the use of zirconium molybdophosphate-99Mo gel

A modified⁹⁹Mo–^99mTc gel generator is described. The present generator uses an insoluble zirconium molybdophosphate (ZrMP) gel tagged with⁹⁹Mo. Molybdenum-99 is chemically combined in the gel structure and cannot be eluted from the matrix. The presence of phosphate increases the chemical stability of the gel and decreases the molybdenum breakthrough. The prepared gel is sufficiently porous to permit ready diffusion of^99mTcO ₄ ^– which can be cluted with saline in yields of up to 90%. The gel was found to contain 25.1% Mo, 21.9% Zr, and 0.7% P in a molar ratio of 1.09:1.0:0.09, respectively. The high molybdenum content of the gel allows the use of cheap, non-polluting (n, )⁹⁹Mo. The eluted^99mTc was of high purity and can be used for medical and pharmaceutical applications.     

Preparation of 99Mo/99mTc generator based on alumina 99Mo-molybdate (VI) gel

In this work alumina ⁹⁹Mo-molybdate (VI) gel is evaluated as a column matrix for use in the preparation of small chromatographic column type ^99mTc generator. Alumina molybdate (VI) gel is prepared by dissolving inactive MoO₃ with aluminum foil in 5 M NaOH solution containing ⁹⁹Mo radiotracer. After complete dissolution, 0.5 H₂O₂ was added to the reaction mixture solution and acidified to pH 5.5 with concentrated HNO₃. The formed AlMo precipitate was washed with NaNO₃ solution, dried at 50 °C for 24 h and then packed in the form of a chromatographic column for elution of the generated ^99mTc radionuclide with physiological saline solution (0.9 % NaCl). Greater than 86 % of the generated ^99mTc activity is immediately and reproducibly eluted with passing 10 mL of the saline solution through 2.0 g of alumina ⁹⁹Mo-molybdate column bed at a flow rate of about 1.0 mL/min. The high radiochemical ≥98.6 % TcO₄ ^?, radionuclidic ≥99.90 % ^99mTc and chemical purities of the eluates satisfy the specifications for use in nuclear medicine.     

Determination of technetium in99Mo/99m Tc-generators

The Tc budget in several ROTOP-generators was determined by neutron activation analysis (NAA) and UV-spectroscopy. The complete procedure included the preparation of the generator, elution cycle in 24 to 72 h intervals and evaporation of the eluates to dryness. The samples were aliquoted, irradiated in the reactor and analyzed via⁹⁹Tc(n, n')^99mTc⁹⁹Tc reaction as well as by UV-absorption due to pertechnetate. The most reliable method proved to be NAA including chemical separation from²⁴Na by ion exchange after the complete decay of³⁸Cl. The detection limit was 50 ppb (3 ng Tc), compared with the total amount of several 10^–5 g down to 10^–7 g Tc in the system and its fractions. The mass balance and the elution profiles obtained correspond very well to the theoretical values. The results permit further quantitative considerations on both elution kinetics and the generator system.     

A novel technique for the separation of99mTc from99Mo

A new technique for the separation of^99mTc from low specific activity⁹⁹Mo is reported. A separation based on the principle of precipitation of⁹⁹Mo as calcium molybdate has been investigated. On precipitating⁹⁹MoO ₄ ^2– from alkaline solution as calcium molybdate under controlled conditions, the^99mTcO ₄ ^– is found to remain quantitatively in the supernatant solution with little carry-over of⁹⁹Mo. This calcium molybdate (⁹⁹Mo) could be redissolved and reprecipitated at regular intervals, yielding^99mTc quantitatively in aqueous neutral solutions. Calcium molybdate precipitates containing up to 1.5 GBq of⁹⁹Mo and 130–180 mg of molybdenum were prepared and evaluated. The performance in terms of repeated^99mTc separation gave yields of 75–93% with acceptable readionuclidic and radiochemical purity.     

99mTc generator with hydrated MnO2 as adsorbent of 99Mo

An ^99mTc generator with MnO₂ as adsorbent of ⁹⁹Mo was investigated. Through batch experiments the retention of ⁹⁹Mo onto MnO₂was studied as a function of the shaking time and the pH value of the ⁹⁹Mo solution. It was found that ⁹⁹Mo showed a retention of 100% onto MnO₂ at the pH range from 3 to 11, and the equilibrium distribution was reached in less than 10 minutes. In column experiments the retention of ⁹⁹Mo onto MnO₂ was also high: 99.72%. In this case, the pH of the utilized ⁹⁹Mo solution was 5. The ^99mTc could be eluted from the MnO₂-⁹⁹Mo column by using either distilled water with a pH of 5 or an aqueous solution of 0.9% NaCl. With the saline solution, the ^99mTc elution yields were higher than 80%, and only one aliquot of 5 ml was needed to get these yields. The best results were obtained when the column was packed with 1 g of MnO₂. The water and the saline solution were passed through the column at a rate of 1.25 ml/min.     

Separation of99Mo from132Te using thiourea as complexing agent. Application to the separation of99Mo from fission products

A radiochemical method to isolate⁹⁹Mo from¹³²Te, both produced in the fission of²³⁵U, has been developed. The method is based on the formation of a cationic complex of tellurium with thiourea in acid medium which is retained (98.7±0.5)% on a cation exchange resin (Dowex 50W-X8, 100–200 mesh), while (99.8±0.05)%⁹⁹Mo passes through it, due to the non-formation of such complex in the same experimental conditions. The radionuclidic purity of⁹⁹Mo was found to be suitable for the preparation of⁹⁹Mo–^99mTc generators. The retention of⁹⁹Mo on an alumina column as a function of pH was investigated and the best pH range for this purpose was found to be 4.0–4.5.     

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.

     

Preparation of99Mo,132Te isotopes and99mTc,132I generators

Adsorption and desorption of⁹⁵Zr−⁹⁵Nb,⁹⁹Mo,¹⁰³Ru,¹³²Te and²³⁹Np in a HCl-alumina system were studied in order to purify⁹⁹Mo and¹³²Te obtained by the cation-exchange separation of fission products and to prepare highly pure^99mTc and¹³²I generators.⁹⁹Mo and¹³²Te, of which radionuclidic purity was over 99.99% and 99.999%, respectively, could be obtained by passing the cation-exchange separated Mo and Te fractions through alumina columns, by washing with HCl and finally by eluting⁹⁹Mo with 1M NH₄OH and¹³²Te with 3M NaOH. In order to raise the recovery of⁹⁹Mo and¹³²Te from the alumina columns, they should be eluted as quickly as possible after the adsorption. The direct use of the alumina column containing⁹⁹Mo or¹³²Te as the generator allowed milking of^99mTc or¹³²I, of which radionuclidic purity was over 99.999%. Milking yields of^99mTc with 0.1M HCl and¹³²I with 0.01M NH₄OH were 77% and 90%, respectively. The latter value was much higher than that in usual performance of the generator.     

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.     

Hydrated titanium dioxide as an adsorbent for99Mo−99mTc generator

The adsorption behaviour of⁹⁹Mo in the form of molybdate and of^99mTc in the form of pertechnetate on hydrated titanium dioxide was investigated at different molarities of hydrochloric acid. The adsorption capacity of molybdate on hydrated TiO₂ is higher than on Al₂O₃. A^99mTc-generator is suggested. This generator is based on the adsorption of (⁹⁹Mo) molybdate on hydrated TiO₂, at acidities of 0.05–0.1M. HCl.^99mTc is eluted with 0.9% NaCl. Radionuclidic, radiochemical and chemical purities of the eluates were checked. This generator seems to have a great potential as compared to the traditional alumina generators.     

Biodistribution of the bone imaging agents99mTc-DHPE and99mTc-MDP in rats

The self life of the freeze-dried formulation kits utilized for the preparation of the new bone imaging radiopharmaceutical^99mTc-1,2-dihydroxy-1,2-bis/dihydroxyphosphinyl/ethane /^99mTc-DHPE/ has been investigated as well as the toxicity of the DHPE. In a biodistribution investigation of^99mTc-DHPE in rats, in comparison to^99mTc-methylenediphosphanate /^99mTc-MDP/,^99mTc-DHPE exhibited a certain extent higher skeleton uptake, a higher blood clearance rate, a very low concentration in other organs, a satisfactory biological stability and excretion primarily through the kidneys. These properties demonstrate that^99mTc-DHPE is a new promising skeleton imaging radio-pharmaceutical.     

Separation of99mTc from parent99Mo by solid-phase column extraction as a simple option for a new99mTc generator concept

Evidence is obtained to show that the liquidliquid extraction separation of^99mTc from⁹⁹Mo with methyl ethyl ketone, methyl propyl ketone and methyl isobutyl ketone can be transformed into a solid-phase column extraction procedure. The aqueous alkaline⁹⁹molybdate solution is immobilized on a column of a granular large-pore diatomaceous earch support, which is the neluted with the abovementioned extractants. Rapid and clean separation of^99mTc can be with all three solvents. The^99mTc can be back-extracted from the organic phase on a column filled with distilled water /or saline/ loaded granular diatomaceous earth /Extrelut^®/. The possibility of using the abovementioned procedure as a basis for a new^99mTc/⁹⁹Mo generator concept is envisaged.     

Comparison of some physicochemical and pharmacokinetical parameters of 99mTc-PAH, 99mTc-MAG3 and 131I-OIH

The purpose of this study was to compare some physicochemical characteristics as well as pharmacokinetic behavior of ^99mTc-PAH, as a novel renal agent, with ^99mTc-MAG₃ and ¹³¹I-OIH. ^99mTc-PAH was prepared from lyophilized kit by adding ^99mTcO₄ ^–. Labeled complex was stabile and high radiochemical purity radiopharmaceutical, with a low percentage of protein bound to human albumin and hydrophilic character. In spite of its smaller renal uptake, ^99mTc-PAH gave satisfactory renal images. ^99mTc-PAH showed faster urinary elimination than ^99mTc-MAG₃ and similar to those one for ¹³¹I-OIH. The comparison of pharmacokinetic parameters of ^99mTc-PAH, ^99mTc-MAG₃ and ¹³¹I-OIH indicated the favorable characteristics of ^99mTc-PAH.     

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.     

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.     

Myocardial reversibility detection. Rest NTG99mTc-MIBI versus201TI reinjection. Preliminary results

This study test whether sublingual administration of nitroglycerin (NTG) could improve the capability of^99mTc-MIBI to detect reversibility in exercise-induced perfusion defects and to compare it with the²⁰¹TI stress-redistribution-reinjection protocol. Twenty-one patients with previous myocardial infarction were submitted to exercise, rest and NTG rest^99mTc-MIBI imaging (3-day protocol). The patients also underwent exercise, redistribution and reinjection²⁰¹Tl myocardial scintigraphy. A total of 273 myocardial segments were analyzed: 76 (28%) had irreversible defects on stress-rest^99mTc-MIBI, 60 (79%) appeared as fixed defects and 16 (21%) were reversible on NTG rest^99mTc-MIBI. Of the 78 myocardial segments with irreversible defects on standard stress-redistribution thallium cardiac imaging, 63 (81%) did not change and 15 (19%) demonstrated enhanced uptake of thallium after reinjection. Data show that rest NTG^99mTc-MIBI study improves the detection of reversible myocardium versus standard exercise/rest^99mTc-MIBI and achieve similar results than²⁰¹Tl reinjection protocol.