[en] 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. (author)

[en] Production of Copper-64 (⁶⁴Cu) by irradiating copper and zinc metals in a reactor was evaluated. Low specific activity ⁶⁴Cu can be easily produced using thermal neutrons via ⁶³Cu (n,γ) ⁶⁴Cu reaction, while use of fast neutrons are mandatory for high specific activity ⁶⁴Cu via ⁶⁴Zn (n,p) ⁶⁴Cu reaction. Natural copper and zinc targets were irradiated in Pakistan Research Reactor-1. Radionuclidic impurities produced by thermal and fast neutrons were determined. Commonly available organic anion exchange resin (AG 1-X8) was used for the separation of no-carrier-added radiocopper from neutron irradiated zinc. More than 95% ^64,67Cu was recovered. The radionuclidic and chemical purity of ⁶⁴Cu was determined. The specific activity of ⁶⁴Cu produced by ⁶³Cu (n,γ) and ⁶⁴Zn (n,p) was compared. (author)

[en] Production of radioactive scandium by irradiating natural titanium metal in Pakistan Research Reactor-1 was evaluated. The production rate of ⁴⁷Sc and other radioactive scandium was estimated. High specific activity ⁴⁷Sc can be produced by irradiating enriched ⁴⁷Ti in sufficient quantities needed for therapeutic applications. A new separation technique based on column chromatography was developed. Neutron irradiated titanium was dissolved in hydrofluoric acid, which was evaporated and taken in distilled water. The resulting solution was loaded on silica gel column. The radioactive scandium comes out first and the inactive titanium is removed with 2 M HCl. More than 95% radioactive scandium was recovered, while chemical impurity of titanium determined by optical emission spectroscopy was less than 0.01 μg/mL in final product. (author)

[en] In present study it is aimed to radiolabel vincristine with ^99mTc and to evaluate bioaffinity of ^99mTc labeled vinc. The optimum conditions required to obtain 99.6 ± 0.4 %, (n = 5) radiolabeling yield of ^99mTc-vincristine (^99mTc-vinc) were as follows: pH 4, 5 µg of vincristine sulphate, 6 µg SnCl₂·2H₂O as a reducing agent and 10 min incubation time at room temperature. Quality control of ^99mTc-vinc was done by using paper electrophoresis and thin layer chromatography. The radiolabeling yield was confirmed by High performance liquid chromatography using radioactive and UV detector operating at 230 nm. ^99mTc-vinc was stable in vitro for 5 h. Biodistribution and scintigraphy of ^99mTc-vinc was performed in mice and rabbits respectively and that ^99mTc-vinc showed high uptake of it in liver and spleen. Finally ^99mTc-vinc may be the potential imaging agent for liver and spleen. (author)

[en] Mitomycin-C is used for the treatment of different types of tumours. In present work, a reliable method was developed for radiolabeling of Mitomycin-C with ^99mTc for diagnostic purpose. ^99mTc-Mitomycin-C was obtained with radiochemical yield of 100 % by adding 200 µg Mitomycin-C, 1 mL (15 mCi) of pertechnetate in 25 μg SnCl₂·2H₂O at pH 7. Labeling efficiency was determined by paper chromatography and ITLC. The charge on ^99mTc-Mitomycin-C was determined by electrophoresis technique. HPLC analyses were performed for the determination of purity of Mitomycin-C and radiochemical purity of labeled complex. Evaluation of ^99mTc-Mitomycin-C, in vitro stability, biodistribution and scintigraphic images in normal mice were performed. (author)

[en] The field of therapeutic nuclear medicine is emerging rapidly as choice of treatment in oncology and other cellular malignancies. The growth of this branch of nuclear medicine is greatly facilitated by the introduction of a number of new radiopharmaceuticals and radionuclides. ⁹⁰Y-radiopharmaceuticals have confirmed their worth in medical and clinical areas in a very short span of time. The ⁹⁰Y is a radioisotope widely used for therapeutic purposes and considerable perfection has been made to understand the chemistry of ⁹⁰Y-labeled radiopharmaceuticals. The development of these radiopharmaceuticals can be made favorable by using appropriate buffer, incubation period, optimal pH, specific activity and reaction temperature. In this review, we have discussed the preparation of range of ⁹⁰Y transporting biological molecules such as antibodies radiolabeled peptides, antigens and microsphere with their clinical applications. (author)