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Capítulo IPEN-doc 29790 In situ characterization of NORM waste from the oil industry2022 - DELLAMANO, J.C.; DAMATTO, S.R.; CARVALHO, R.N.; MENEGHINI, A.A.; MARUMO, J.T.; MADUAR, M.F.; VICENTE, R.In the oil industry, radioactive wastes are generated in the oil production platforms containing natural radionuclides, such as 226Ra and 228Ra, the NORM waste. This waste is mainly in the form of produced water, sludge and scales which should be characterized for the correct final destination. The Brazilian laws establish that the NORM wastes from the oil production must comply with Law 10308 of November 20, 2001, which determine in its article 7, "The disposal of radioactive waste of any kind in the oceanic islands, the continental shelf and the Brazilian territorial waters is prohibited." Therefore, the NORM waste from offshore oil extraction rigs should be transported to onshore facilities. There are two options for the destination of this material: industrial landfill, in the case of activity concentrations are below clearance limits established by Brazilian Nuclear Commission, CNEN; or on the contrary, to intermediate storage facilities, until final disposal is decided. Currently, the oil production companies take samples from the waste and send them to radiometric laboratories in order to evaluate their activity concentration by gamma spectrometry. The complete process takes more than six months to be concluded. Nuclear and Energy Research Institute, IPEN, is making efforts to solve the management problems of NORM waste from oil extraction, including conduct research aiming at characterizing the waste. The objective of the paper is to present the results of in situ characterization of drums containing oil sludge using portable gamma spectrometers.Resumo IPEN-doc 25908 Gamma ray spectroscopy studies on low and intermediate level radioactive waste from Angra-1 nuclear power plant2018 - SILVA, PAULO S.C. da; ZAHN, GUILHERME S.; CARVALHO, RICARDO N. de; GENEZINI, FREDERICO A.The determination of the radionuclide composition of low - and intermediate - level radioactive waste is of paramount importance for the design and implementation of Brazil`s planned radioactive waste repository. While there is some knowledge of the radionuclides expected to be present, the exact activity values in each of the waste bins are not determined with su±cient precision, so theres an ongoing e®ort to analyze the composition of this waste and make the radioactive inventory of the bins containt, which comprises several institutions and laboratories. In the present work the gamma - ray spectroscopy of samples of resin, ¯lters and evaporator concentrate from Angra 1 nuclear power plant have been studied. Small aliquots (» 500 mg) of the distinct samples were stored in glass vials and gamma- counted in a characterized high resolution germanium detector. In order to determine the best counting time, these aliquots were counted for 24h (real - time), with the spectroscopy results saved after each full hour of counting. The resulting twenty four spectra were then analyzed with Canberras Genie - 2000 software, using ISOCS e±ciency correction tool. The results for each sample were then compared to determine the required counting time for each of the radioisotopes of interest.