VANESSA MORAES
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Resumo IPEN-doc 24683 Production of 57Co, 109Cd, 111In and 117mSn using CV-28 cyclotron at IPEN-CNEN/SP2001 - OSSO JUNIOR, J.A.; LANDINI, L.; LION, L.F.; MORAES, V.Several radioisotopes produced in Cyclotrons have physical properties of decay suitable to be used as: radiopharmaceuticals, for in vivo Diagnosis images (with the techniques of SPET and PET, Single Photon Emission Tomography and Positron Emission Tomography, respectively) and for Therapy, in Nuclear Medicine; calibration sources of several instruments applied in the nuclear area and in Metrology; and as radioactive tracers of elements investigated in many fields, such as Chemistry, Physics and Biology. This work describes the production of four of these radioisotopes that are very important in these areas: 57Co, 109Cd, 111ln and 117mSn. They can be obtained using the CV-28 Cyclotron at IPEN, because it can accelerate proton beams with energies up to 24MeV and currents up to 20μA (external). 57Co (t1/2=271.3 d) decays by electron capture to 57Fe with the emission of γ-rays and one characteristic X-ray. It is widely used as calibration source of detectors such as: Ge(Li), Ge(HP), Nal(TI) and dose calibrators (well type detectors). Besides these applications, 57Co Flood Sources are used to test the response uniformity of gamma cameras, in Nuclear Medicine. 109Cd has a half-life of 462.6 d and decays by electron capture to 109Ag with the emission of one γ-ray and one characteristic X-ray. This radioisotope can be employed as calibration source of X-ray and γ-rays detectors; as a radioactive tracer of Cd, an environment pollutant and used in the EDXRF (Energy Dispersion X-Ray Fluorescence) technique. 57Co was produced through the irradiation of natNi. Thick target yields for 55Co, 56Co, 57Co, 58CO, 56Ni and 57Ni were measured and the mean values were 346.69kBq/μA.h (9.37μCi/μA.h), for the direct production of 57Co and 150.59kBq/μA.h (4.07μCi/μA.h), through the decay of 57Ni (11.31 days after EOB - End of Bombardment). A solution of 57CoCl2 was prepared, to fill a flood source for calibration of gamma camera, with activity of 222MBq (6mCi) of 57Co and impurity levels of 1.13 and 1.29% for 56Co and 58Co, respectively, at delivery time. In order to achieve these results, a chemical separation method was developed with a separation yield of 93% for 5'7Co and a negligible loss of Ni. A composite target of Ni and Ag was prepared and a chemical separation method proposed to allow the separation between the targets and the products of interest, 57Co and 109Cd. The yields obtained in the irradiation of the composite target were: 947.94kBq/μA.h (25.62μCi/μA.h) of 57Co - direct reaction, 259-00kBq/μA.h (7μCi/μA.h) of 57Co - indirect reaction (11.31 days after EOB) and 71.41kBq/μA.h (1.93μCi/μA.h) of 109Cd, which showed the efficiency of its use, as well as the chemical separation, with a yield of 80% for 57Co and 109Cd. 111ln (t1/2=67.5 h) has appropriate characteristics for Diagnosis in Nuclear Medicine due to its decay mode (100% by electron capture) and its adequate half-life to slow biological studies, that makes it one of radioisotopes of interest of Brazilian Physicians. It can also be used in angular correlation studies in Nuclear Physics. 111In was produced by the 112Cd(p,2n)111ln reaction, that has the highest yield. The Cd targets were prepared by electroplating of CdSO4 solution in copper and copper/nickel backings. After being irradiated, a chemical separation was performed by an acetic acid extraction method, with an overall recovery yield for 111ln higher than 95%. The level of the chemical impurities of Cd, Ni and Cu were bellow than the permissible values. 117mSn (t1/2=14 d) has suitable characteristics of decay to be used as a tracer of SnCl2 in the labeling of organic molecules with 99mTc and also in radiotherapeutical applications. It was prepared by the irradiation of natural tin through the nuclear reactions natSn(p,xn)117Sb→117mSn. The production thick target yield of 117mSnnn was 784.4kBq/μA.h (21.20μCi/μA.h) and with the proper decay time of its precursor, 117Sb, no radionuclidic impurities appeared in the final product. A chemical separation method was developed to separate first 117Sb from the irradiated Tin and then 117mSn from Sb with a good chemical yield. The quality control procedures showed the good quality of the final product, 117mSn.Artigo IPEN-doc 10616 Estudo do desempenho de geis de molibdenio com titanio no preparo de geradores de sup(90)Mo-sup(99m)Tc2005 - MORAES, V.; OSSO JUNIOR, J.A.Artigo IPEN-doc 08822 Estudo do desempenho do gel de molibdenio com titanio para utilizacao nos geradores de sup(99)Mo/sup(99m)Tc2002 - MORAES, V.; NIETO, R.C.; CAMARGO, F.; OSSO JUNIOR, J.A.Artigo IPEN-doc 08820 Estagio atual do projeto de preparo do gel de molibdato de zirconio para uso nos geradores de sup(99)Mo/sup(99m)Tc2002 - OSSO JUNIOR, J.A.; SILVA, N.C.; LIMA, A.L.V.P.; CAMARGO, F.; NIETO, R.C.; MORAES, V.; LANDINI, L.O projeto de preparo do gel de Molibdato de Zircônio, para uso nos geradores de 99Mo/99mTc, faz parte das diretrizes do IPEN de nacionalização da produção de radioisótopos empregados em Medicina Nuclear. Atualmente, o 99Mo usado nos geradores distribuídos pelo Instituto é importado e produzido pela fissão do 235U. Este trabalho mostra a situação atual do referido projeto, no qual o 99Mo será produzido pela reação 98Mo(n,g) 99Mo, utilizando-se o Reator IEA-R1m do IPEN e, posteriormente, submetido a uma reação química com o Zr, sob condições adequadas para formar o gel de Molibdato de Zircônio. Neste trabalho, também são apresentados os resultados dos testes realizados com os experimentos da planta piloto de preparo do gel de Molibdato de Zircônio. Estes resultados são comparados com aqueles obtidos no processo desenvolvido em laboratório, onde algumas variáveis foram estudadas, como: pH final da solução que contém o gel, concentração inicial das soluções de Mo e Zr, temperatura de reação e ordem de adição dos reagentes. Uma previsão da produção rotineira dos geradores de 99Mo/99mTc também é exibida.Artigo IPEN-doc 09097 The influence of a coal-fired power plant operation on radionuclide concentrations in soil2002 - FLUES, M.S.M.; MORAES, V.; MAZZILLI, B.P.Artigo IPEN-doc 11181 Liquid kit for preparation of sup(188) rhenium-etidronate2005 - MARCZEWSKI, B.; DIAS, C.R.; MORAES, V.; OSSO JUNIOR, J.A.The aim of this study was the preparation of a liquid kit for radiolabeling of 188Re-HEDP (hydroxyethylidene diphosphonate). 188Re was obtained from alumina based 188W/ 188Re generators. This paper reports the efficacy of a cold kit stored for more than two weeks, determined by the dependence of the radiolabeling yields of 188Re-HEDP on the incubation time, reducing agent concentration, the effects of concentration of ligand, the pH of the reaction and the temperature. The cold kits showed a good stability when carrie-free rhenium-188 was added in the reaction mixture.Artigo IPEN-doc 11184 Study of gels of molybdenum with cerium in the preparation of generators of sup(99)Mo - sup(99m)Tc2005 - MORAES, V.; MARCZEWSKI, B.; DIAS, C.R.; OSSO JUNIOR, J.A.99m Tc has ideal nuclear properties for organ imaging in nuclear medicine, and it is obtained from the 99Mo99m Tc generator. Four different types of generators are available: chromatographic that uses 99Mo from fission of uranium; MEK solvent extraction; Tc2O7 sublimation; gel chromatographic. This work presents the preparation of gel generators of molybdenum with cerium and characterization of the gels: mass ratio between molybdenum and cerium, structure, size of particles and elution percentage of 99m Tc after irradiating the gels. Eight gels were prepared at the same temperature of 50 ºC with concentrations of NaOH of 2 and 4 mol/L, mass ratio of 0.31 and 0.38 and final pH of 3.5 and 4.5. The analysis of the results proved that these gels are not adequate for preparation of the generators of 99Mo99m Tc, since the elution percentages are low, when compared with the gel of molybdenum with zirconium.Artigo IPEN-doc 11183 Tc-sup(99m) direct radiolabeling of monoclonal antibody I or egf/r3: quality control and image studies in mice2005 - DIAS, C.R.; MARCZEWSKI, B.; MORAES, V.; BARBOZA, M.F.; OSSO JUNIOR, J.A.Monoclonal antibodies (Mabs) have been useful for immunoscintigraphic applications in clinical diagnosis since they were introduced in the practice of nuclear medicine. The ior egf/r3 (Centis, Cuba) is a murine monoclonal antibody against epidermal growth factor receptor (EGF-R) and has been widely used in the radioimmunodiagnosis of tumors of epithelial origin. Labeled with 99mTc, its main application in Nuclear Medicine is the follow up, detection and evaluation of tumor recurrences. The objective of this work is to describe the preparation of a lyophilized formulation (kit) for radiolabeling the Mab ior egf/r3 with 99mTc for immunoscintigraphic applications. Radiolabeling efficiency, effects on immunoreactivity, image studies and stability of the formulation are reported. The study demonstrated that the kit formulation can be labeled with 99mTc at high yields and can be used to visualize in vivo human tumors of epithelial origin by immunoscintigraphy studies.