Synthesis of <Superscript>131</Superscript>I labeled estrone derivatives and biodistribution studies on rats

Summary The aim of this study is to synthesize novel ¹³¹I labeled estrone derivatives that may have therapeutical potentials on Estrogen Receptor rich tumors. Two radiolabeled estrone derivatives, [¹³¹I]2-iodo-3-methoxy-estra-1,3,5-trien-17-one and [¹³¹I]4-iodo-3-methoxy-estra-1,3,5-trien-17-one were synthesized. Ether amino estrone derivatives were obtained from estrone in three steps by means of diazonium compounds. Tissue distribution studies exhibited receptor-mediated uptake in target organs in female Albino Wistar rats. Maximum uptakes for 2-iodo[¹³¹I]-3-methoxy-estrone are in stomach, pancreas, intestines and uterus. A similar biodistribution profile was obtained for 4-iodo[¹³¹I]-3-methoxy-estrone. However 2-iodo-3-methoxy-estra-1,3,5-trien-17-one has higher uptake in stomach, kidneys, pancreas, and intestines than 4-iodo-derivative.     

Volume efficiency correction factor determination for gamma spectrometry using <Superscript>82</Superscript>Br

An easy experimental method for volume efficiency correction factor determination in gamma spectrometry was evolved in this work using ⁸²Br volume samples. The ⁸²Br point sample was diluted successively to form cylindrical samples of different volumes. The gamma spectra of these samples were measured before and after dilution for different sample—detector spacing. The theoretical basis of this method is simple. The volume efficiency dependence on the radius and height was determined.     

Determination of calibration curves for <Superscript>131</Superscript>I in thyroid tumour metabolic radiotherapy and other radionuclides used in SPECT imaging

Large columns containing aluminum oxide (Al₂O₃) or gel (e.g. zirconium molybdate) are needed to prepare ⁹⁸Mo(n,γ)⁹⁹Mo→^99mTc column chromatographic generators that results in large elution volumes containing relatively high ⁹⁹Mo impurity and low concentrations of ^99mTc. The decrease in radioactive concentration or specific volume concentration of ^99mTc places a limitation on some pharmaceutical kits (DTPA, MIBI, ECD, etc.) or clinical procedures. We report on the post elution concentration of ^99mTc using in house prepared lead cation-exchange and alumina columns. Using these columns high bolus volumes (10–60 mL 0.02M sodium sulfate) of ^99mTc can conveniently be concentrated in 1 mL of physiological saline. This approach also works very effectively to prepare high specific volume solutions of ^99mTc-pertechnetate from a fission based ⁹⁹Mo/^99mTc generator in the second week of its normal working life.     

Synthesis and preliminary biodistribution studies of [<Superscript>131</Superscript>I]SIB-PEG<Subscript>4</Subscript>-CHC in tumor-bearing mice

This work reports the synthesis and preliminary biodistribution results of [¹³¹I]SIB-PEG₄-CHC in tumor-bearing mice. The tributylstannyl precursor ATE-PEG₄-CHC was synthesized by conjugation of ATE to amino pegylated colchicine NH₂-PEG₄-CHC. [¹³¹I]SIB-PEG₄-CHC was radiosynthesized by electrophilic destannylation of the precursor with a yield of ~44%. The radiochemical purity (RCP) appeared to be >95% by a Sep-Pak cartridge purification. [¹³¹I]SIB-PEG₄-CHC was lipophilic and was stable at room temperature. Biodistribution studies in tumor-bearing mice showed that [¹³¹I]SIB-PEG₄-CHC cleared from background rapidly, and didn’t deiodinate in vivo. However, the poor tumor localization excluded it from further investigations as a tumor-targeted radiopharmaceuticals.     

Separation of <Superscript>133</Superscript>Xe from <Superscript>99</Superscript>Mo, <Superscript>131</Superscript>I and uranium,and removal of impurities using gas chromatography

Summary Separation and purification of ¹³³Xe from acidic solution containing uranium, ⁹⁹Mo and ¹³¹I has been developed. In the first step of this work, uranium pellets were dissolved under pressure (8-15 bar) in 8M nitric acid solution. Then¹³³ Xe and other gases were conducted to activated charcoal cold trap. Final purification of ¹³³Xe from impurities such as NO_x, radioiodine and krypton was performed by passing through a molecular sieve preparative chromatographic column using helium as mobile phase. The final recovery of ¹³³Xe from the separation-purification process was higher than 98%. Adsorption-desorption behavior of radioxenon on the charcoal and molecular sieves have also been studied and discussed.     

Leaching kinetics of <Superscript>54</Superscript>Mn and <Superscript>89</Superscript>Sr radionuclides fixed in cement­vermiculite composition

Summary Leach characteristics of ⁵⁴Mn and ⁸⁵Sr radionuclides from ordinary Portland cement have been studied using International Atomic Energy’s (IAEA) standard leach method. The retardation factors, K_F, and coefficients of distribution, k_d, have been determined using a simplified mathematical model for analyzing the migration of radionuclides. The lowest leaching values after 60 days were achieved in samples with 5% of vermiculite. Results presented in this paper are the examples of results obtained in a 10 year mortar and concrete testing project, which will influence the design of the engineered trench system for a future central Serbian radioactive waste storage center.     

SDAT: analysis of <Superscript>131m</Superscript>Xe with <Superscript>133</Superscript>Xe interference

The Spectral Deconvolution Analysis Tool (SDAT) software was developed at The University of Texas at Austin. SDAT utilizes a standard spectrum technique for the analysis of β–γ coincidence spectra. Testing was performed on the software to compare the standard spectrum analysis technique with a region of interest (ROI) analysis technique. Experimentally produced standard spectra and sample data were produced at the Nuclear Engineering Teaching Laboratory (NETL) TRIGA reactor. The results of the testing showed that the standard spectrum technique had lower errors than the ROI analysis technique for samples with low counting statistics. In contrast, the ROI analysis technique outperformed the standard spectrum technique in high counting statistics samples. It was also shown that the standard spectrum technique benefitted from a compression of the number of channels within the spectra.     

Technology of DTPA and immunoglobulins conjugation and their attachment to <Superscript>90</Superscript>Y and <Superscript>177</Superscript>Lu radionuclides

The aim of the study of labeling of ligand–antibody conjugates was to find optimal conditions of preparing of these conjugates and appropriate radioactivity of selected nuclide for applications in nuclear medicine. Conjugation of the γ-immunoglobulin G (human or bovine IgG, polyclonal antibodies) and bifunctional chelating agent, diethylenetriaminepentaacetic acid dianhydride (cDTPAA), was carried out. Various values of the cDTPAA/antibody ratio, the weight concentration of polyclonal or monoclonal antibodies (MEM-97) and buffers were used. Further, the labeling conditions of the DTPA–IgG conjugate by radionuclides ⁹⁰Y and ¹⁷⁷Lu were optimized, and the labeling yield and the conjugation ratio of prepared radionuclide–DTPA–IgG conjugates was determined. Optimal incubation time of the immunoglobulin conjugation was obtained at 30 min from mixing of individual components. The labeling yield of radionuclide–DTPA–antibody conjugate higher than 95% was achieved. Higher values of conjugation ratio of radionuclide–DTPA–antibody conjugate were achieved in 0.1 mol L⁻¹ carbonate buffer, pH 8.5, and the 0.1 mol L⁻¹ carbonate buffer is suitable for studied conjugation systems. This study showed that the labeling yield as well as the conjugation ratio of tested systems depend on the amount of antibody substance, bifunctional chelating agent/antibody molar ratio and pH value of the buffer used.     

Simultaneous measurements of cosmogenic radionuclides <Superscript>32</Superscript>P, <Superscript>33</Superscript>P and <Superscript>7</Superscript>Be in dissolved and particulate forms in the upper ocean

A technique to determine concentrations of ³²P, ³³P and ⁷Be in dissolved and particulate forms, in the upper ocean was developed. By using a large volume in situ filtration and concentration system (LV-FiCS), several tons of seawater at different depths were filtered concurrently through two kinds of filters. The dissolved radionuclides were concentrated onto adsorbents in the LV-FiCS. The radionuclides obtained were further purified by precipitation and ion-exchange chromatography, and quantified by gamma-spectrometry and ultra-low level liquid scintillation counter measurements. The technique was used with good results in a coastal area of Ibaraki, Japan.     

Preparation and biodistribution of [<Superscript>131</Superscript>I]linezolid in animal model infection and inflammation

Linezolid is the first of new class of antibiotics, the oxazolidinones, and exhibits activity against many gram-positive organisms, including vancomycin-resistant Enterococcus faecium, methicillin-resistant Staphylococcus aureus, and penicillin-resistant Streptococcus pneumoniae. Aim of the study: Linezolid was to label with I-131 and potential of the radiolabeled antibiotic was to investigate in inflamed rats with S. aureus (S. aureus) and sterile inflamed rats with turpentine oil. Linezolid was labeled with I-131 by iodogen method. Biodistribution of [¹³¹I]linezolid was carried out in bacterial inflamed and sterile inflamed rats. Radiolabeling yield of [¹³¹I]linezolid was determined as 85 ± 1% at pH 2. After injecting of [¹³¹I]linezolid into bacterial inflamed and sterile inflamed rats, radiolabeled linezolid was rapidly removed from the circulation via the kidneys. Binding of [¹³¹I]linezolid to bacterial inflamed muscle (T/NT = 77.48 at 30 min) was five times higher than binding to sterile inflamed muscle (T/NT = 14.87 at 30 min) of rats. [¹³¹I]linezolid showed good localization in bacterial inflamed tissue. It was demonstrated that [¹³¹I]linezolid can be used to detect S. aureus inflammation in rats.     

Modeling β-γ coincidence spectra of <Superscript>131m</Superscript>Xe, <Superscript>133</Superscript>Xe, <Superscript>133m</Superscript>Xe,and <Superscript>135</Superscript>Xe

In support of the Comprehensive Nuclear-Test-Ban Treaty (CTBT), improvements have been made to the model of the Automated Radioxenon Sampler/Analyzer (ARSA) β-γ coincidence detector for radioxenon monitoring. MCNPX is used to simulate the detector response for all the electrons and photons emitted from ^131mXe, ¹³³Xe, ^133mXe, ¹³⁵Xe, and ¹³⁷Cs signals. A MatLab code was written to incorporate the MCNPX results in the calculation of β-γ coincidence spectra. These will aid in the development of the Spectral Deconvolution Analysis Tool (SDAT)¹ and to calibrate β-γ coincidence systems. The models developed for this work include improvements over previous models in their ability to address Compton scattering in the β-cell, and the β-distribution offset in the 31 keV γ-ray region for ¹³³Xe.     

Studies on the adsorption of <Superscript>125</Superscript>I on bromide coated silver rods for the preparation of <Superscript>125</Superscript>I-seeds for brachytherapy applications

This article presents the development, the testing and the efficiency estimation of a system for the monitoring of the atmospheric concentration of radon using a detector ionization chamber type in pulse mode for environmental measurements in which the measurement of the average value of the ionization current is completed with the recording of the impulses of the ionization current caused by the alpha disintegrations from the sensible volume of the detector.     

A perspective on <Superscript>99m</Superscript>Tc and <Superscript>125/131</Superscript>I labeled receptor targeted compounds and their in vitro/in vivo affinities

A novel quinoline derivative, 2,2′-[(5-chloro-8-hydroxyquinoline-7-yl) methylazanediyl] diacetic acid (CHQMADA) was labeled with ^99mTc using SnCl₂·2H₂O as a reducing agent to give a complex with a labeling yield 94 %. Also [^99mTc(H₂O)₃(CO)₃]⁺ was prepared by heating at 100 °C for 30 min using 2 mg CHQMADA at pH 8 to give a labeling yield >99 %. ^99mTc-(CO)₃ CHQMADA and ^99mTc-Sn(II)-CHQMADA showed tissue uptake (target to non target T/NT = 6.80 ± 0.22) and (T/NT = 5.65 ± 0.34) respectively in Escherichia coli induced infection, which is higher than the commercially available ^99mTc-ciprofloxacin (T/NT = 3.80 ± 0.80). In conclusion, both complexes were able to differentiate between septic and aseptic inflammation with superiority of [^99mTc-(CO)₃ CHQMADA].     

Determination of <Superscript>237</Superscript>Np, <Superscript>93</Superscript>Zr and other long-lived radionuclides in medium and low level radioactive waste samples

The majority of long-lived radionuclides produced in the nuclear fuel cycle can be regarded as “difficult-to-measure” nuclides, hence chemical separation is needed before the nuclear measurement of them. A combined radiochemical procedure that enables the simultaneous determination of some “difficult-to-measure” nuclides in medium and low level radioactive wastes has been developed in our laboratory. Recently, this method has been extended for determination of ²³⁷Np and ⁹³Zr. ²³⁷Np and ⁹³Zr are pre-concentrated by co-precipitation on iron(II) hydroxide and zirconium oxide, separated by extraction chromatography using UTEVA, and measured by inductively coupled plasma mass spectrometry (ICP-MS). As even traces of polyatomic ions and isotopes at m/z 237 or 93 cause considerable interferences during ICP-MS detection, a purification step by extraction chromatography was needed. Analyzing real samples (evaporation concentrates of a nuclear power plant) 66–99% and 31–99% chemical yields were achieved for Np and Zr, respectively.     

Radioiodinated magnetic targeted carriers (<Superscript>131</Superscript>I-MTC)

Magnetically targeted drug delivery by particulate carriers is an efficient method of delivering drugs to localized disease sites, such as tumors. Thus, high concentrations of carrier molecules such as therapeutic radiopharmaceuticals can be achieved near the target site without any toxic effects to normal surrounding tissue. In this study, magnetic targeting carriers (MTC) were radioiodinated with ¹³¹I using three different methods (1) ¹³¹I was directly bound onto MTC, (2) an iron complex of 8-hydroxyquinoline (8-OHQ) has been absorbed onto magnetic microspheres. The iodogen method was performed for the iodination of the complexes. (3) 8-OHQ was radioiodinated before chelating with Fe. Reaction parameters were investigated in order to optimize the final properties of the labeled MTC. The best labeling yield and the best stability were obtained when 8-OHQ was chelated before the radioiodination. Binding efficiency was found to be 99.58%. The labeling of the MTC with ¹³¹I was undertaken to allow for therapy with ¹³¹I-labeled MTC with simultaneous imaging.     

Evaluation of infection imaging potential of <Superscript>131</Superscript>I-labeled imidazolium salt

Effective antimicrobial compounds are necessary due to increased resistance of antibiotics against microorganisms causing infectious diseases. In this study, imidazolium-TFSI salt [ITFSI: octyl-bis(3-methylimidazolium)-di(bis(trifluoromethane)sulfonimide)] was labeled with ¹³¹I with high efficiency. In vitro uptake experiments of ¹³¹I-ITFSI showed high uptake in gram-positive Staphylococcus aureus bacteria. ¹³¹I-ITFSI was also evaluated for comparison between bacterial infection and sterile inflammation by in vivo studies. The biodistribution results revealed that ¹³¹I-ITFSI might be used as a nuclear imaging agent for detection of bacterial infection.     

Determination of <Superscript>90</Superscript>Sr, <Superscript>129</Superscript>I and gross beta radioactivity concentration in some teas

In this study, ⁹⁰Sr (540 keVβ ⁻), ¹²⁹I (150 keVβ ⁻) and the gross beta radioactivity concentrations were determined for the samples of tea as the most leading consumed hot drink in the markets (processed and packaged for sale) in our country. Furthermore, the obtained data were statistically analyzed. For determination of ¹²⁹I (150 keVβ⁻), ⁹⁰Sr (540 keVβ⁻) and gross radioactivity concentrations in tea samples, a sensor system consisting of scintillation detector with BP4 probe sensitive to beta radiation and a radiation meter (ST7) configurable for windows at desired power was used.     

Disequilibrium of dissolved <Superscript>234</Superscript>U/<Superscript>238</Superscript>U and <Superscript>210</Superscript>Po/<Superscript>210</Superscript>Pb in Greek rivers

For the first time, a radiological study for the dissolved ²³⁸U, ²³⁴U, ²¹⁰Pb and ²¹⁰Po was held in major Greek rivers across the country. ²³⁴U/²³⁸U activity ratios are above one in all samples and ²¹⁰Po/²¹⁰Pb activity ratios are respectively below the unit indicating the disequilibrium in the samples. Quite satisfactory correlations were observed among ²³⁴U and ²³⁸U as well as among ²¹⁰Po and ²¹⁰Pb values. Uranium isotopes were separated by ion exchange and electroplated on stainless steel plates. ²¹⁰Po was spontaneously deposited on nickel plates, while ²¹⁰Pb was indirectly determined through the ingrowth of ²¹⁰Po. The sources were measured by a-spectrometry.