[en] The preparation of ⁹⁹Mo-,sup(99m)Tc generator based on the adsorption of ⁹⁹Mo on hydrous zirconium oxide column, employing the in exchange technique, is described. The adsorption of ⁹⁹Mo on hydrous zirconium oxide (HZO) and the separation of sup(99m)Tc, generated by the decay of ⁹⁹Mo with saline solution, are analised. The sup(99m)Tc separation yield, pH of the eluted solution, aspect of the elution curve and the adsorption of ⁹⁹Mo on hydrous zirconium oxide calcined at 800⁰C are studied. The chemical and radioactive purities of the final product are analysed and the variation of the elution yield for successive elutions is studied. (Author)

[en] The ideal conditions to produce ¹²³I through the ¹²⁴Te (p,2n) ¹²³I reaction at the CV-28 cyclotron of IPEN-CNEN/SP (protons , E_max 24MeV) were studied in this work. Two target materials were tested: pure TeO₂ and TeO₂ with 2%Al₂O₃. The chemical separation of ¹²³I was carried out by a dry distillation process with a high frequency induction furnace. The results obtained up to now show the best separation yields (80%) in the following conditions: 1) Target: pure TeO₂; 2) Furnace temperature: 760±5⁰C; 3) Diffusion time: 2 min; 4) Oxygen flux rate: 30-40ml/min. (author)

[en] ²⁰¹ Tl was obtained in cyclotron by irradiating natural targets of mercury and of thallium with protons. A study of thallium 201 preparation methods was made, since the targets preparation, the chemical separation techniques, until the quality controls of the ²⁰¹ T L C L final solution and the thallium recovery experiments. The results showed in both the thallium preparation methods (direct and indirect) permit to conclude that is is impossible to produce ²⁰¹ T L at IPEN. (author)

[en] Full text: The Energetic and Nuclear Research Institute (IPEN), owned by National Commission of Nuclear Energy (CNEN), is a non-profit government institution that produces on a national scale more than 18 radioisotopes and radiopharmaceuticals for nuclear medicine. These radiopharmaceuticals are used in the diagnosis and treatment of more than 1.5 million people in Brazil. This level of production was achieved through the creation of new technologies and automation solutions, because of the difficulty and cost on importation of raw materials and labeling compounds ready for use. In Brazil, only CNEN has authorization to import, manipulate and distribute radiopharmaceuticals. Therefore, the quality of those radioisotopes must comply with international specifications and regulations. Much research and 40 years of improvements has won IPEN international approval for the radiopharmaceuticals that it produces, and quality standards and specifications are today as good as in any other developed country. IPEN has even developed a few solutions in radioisotope production for others countries, such as Cuba and soon Peru. The first step towards self-production was the acquisition of a cyclotron (Cyclone-30) and the improvement of the reactor power from 2 MW to 5 MW. Many technical visits were made to radiopharmaceutical institutions around the world with the purpose of bringing self-reliance and self-development solutions to IPEN. The international radiopharmaceutical community has always contributed to this effort, and only with their help our self-development and self-reliance could be possible. IPEN has ISO 9001-2000 certification and has made efforts to improve the installations in order to achieve Good Manufacturing Practice. Every effort we make today has the goal of making radiopharmaceuticals available for therapy at the most competitive price possible for our institution. (author)

[en] The idel conditions to produce ¹²³I via ¹²⁴Te(p,2n)¹²³I reaction at the CV-28 cyclotron of IPEN-CNEN/SP (protons, E_max= 24 MeV) were studied in this work. Two target materials were tested: pure TeO₂ and TeO₂ with 2% Al₂O₃. The chemical separation of ¹²³I was carried out by a dry distillation process with a high frequency induction furnace. The results obtained up to now show the best separation yields (80%) in the following conditions: 1) Target: pure TeO₂; 2) Furnace temperature: 760±5^oC; 3) Diffusion time: 2 min; 4) Oxygen flux rate: 60 ml. (author) 1 fig., 1 tab., 2 refs

[en] The improvements performed on the routine production of sup(99m) Tc-generators at the Instituto de Pesquisas Energeticas e Nucleares-CNEN/SP, are described. The old model generators (manual elution of sup(99m) Tc) were substituted by automatically eluted generators (Vacuum system). The alumina column, elution system and acessories were modified; the elution time was reduced from 60 to 20-30 seconds. The new generators give 80-90% elution yields using six mililiters of sodium chloride 0,9% as sup(99m) Tc eluant instead of the 10 mililiters necessary to eluate the old generators. So, the radioactive concentrations are now 70% higher. The radioactive, radiochemical, chemical and microbiological criteria were examinated for sup(99m) Tc solutions. Like old generators, automatic generators were considered safe for medical purpose. (Author)

No abstract available

[en] The objective of this work is to present the radiological safety criteria, adopted in the TP, by the gradual increase of demand of radionuclides in the applications you prescribe, as well as the practical solutions to adapt the already existing laboratories, caused to such demand, that guarantee the sure operation of the installation. It is concluded that the levels of radiation dose can be reduced with the introduction of alterations in the hot cells design and in the system of residues management radio-active, as well as by means of efforts in the application of an effective practice code

[en] A comparative study from a theoretical yield of main radioisotope production, used in nuclear medicine is presented. The obtained values in cyclotron-C-V- 28, Ep ≤24 MeV are compared with the possible values of a cyclotron with Ep=30 MeV. (C.G.C.)

[en] Radioisotope ¹⁰⁹ Cd is widely used as radiation source x-fluorescent and gamma spectrometry analysis. In this work natural silver foils were proton irradiated in the CV-28 cyclotron at IPEN-CNEN/SP. After irradiation it was analysed the yield of the Ag(p,n)¹⁰⁹ Cd reaction in function of incident proton energy. The method used for the chemical separation of ¹⁰⁹ Cd from silver targets is based in the removal of silver by precipitation with copper metal and the cadmium is separated from other elements by anion exchange chromatography. (author)