ROBERTO VICENTE

Resumo

Degree in Physics from Universidade de São Paulo (1977); master degree in Nuclear Technology from Universidade de São Paulo (1980) and doctorate in Nuclear Technology from Universidade de São Paulo (2002). Has experience in radioactive waste management, acting on the following subjects: radioactive waste characterization, treatment and disposal; disposal of disused sealed radioactive sources. (Text obtained from the Currículo Lattes on November 25th 2021)


É bacharel em Física pela Universidade de São Paulo (1977), tem mestrado em Tecnologia Nuclear pela Universidade de São Paulo (1980) e doutorado em Tecnologia Nuclear pela Universidade de São Paulo (2002). Atualmente é tecnologista da Comissão Nacional de Energia Nuclear. Tem experiência na área de Engenharia Nuclear, com especialização em Gestão de Rejeitos Radioativos, atuando principalmente nos seguintes temas: gerenciamento, tratamento e deposição de rejeitos radioativos. (Texto extraído do Currículo Lattes em 25 nov. 2021)

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  • Artigo IPEN-doc 29125
    Evaluation of recovery yields of 60Co and 137Cs in extraction procedures
    2022 - ALMEIDA, M.A.; AYLLON, R.M.; ANGELINI, M.; VICENTE, R.; SILVA, P.S.C.
    Nuclear technology has been implemented in several sectors of society, among them, it is possible to highlight medicine, industry, research, among others. The high demand of these nuclear applications has caused problems with regard to the generation of radioactive waste. The laser ablation method has been pointed out in the last years for the decontamination of surfaces and the contamination removed is completely retained in paper filters. This requires a safe and inexpensive method to perform the characterization of the radioisotopic inventory present in the laser filter samples. In this study, the extraction and quantification of the radionuclides present in the filter was evaluated using 60Co and 137Cs radionuclides. Two forms of extraction were tested: with Soxhlet equipment and by digesting the filter samples in a beaker, both using 3M HNO3 as extractant. The chemical yield was calculated using gamma ray countings obtained before and after extraction. It was observed that the extraction method by digesting the filter directly in a beaker presented the highest yield recovery results.
  • Artigo IPEN-doc 27719
    Knowledge management in the decommissioning of nuclear facilities in Brazil
    2020 - SMITH, R.B.; SALVETTI, T.C.; TESSARO, A.P.G.; MARUMO, J.T.; VICENTE, R.V.
    In the second half of the twentieth century in Brazil, several nuclear facilities were built for the most varied objectives. The largest number of such facilities is at the Nuclear and Energy Research Institute in São Paulo (IPEN-CNEN/SP). For different reasons, some of these facilities had their projects finalized and were deactivated. Some of the equipment was then dismantled, but the respective nuclear and radioactive material remained isolated in the original sites waiting for the proper decommissioning procedures. The Celeste Project is an example of a facility where the nuclear material has been kept, and is subject to Argentine-Brazilian Agency for Accounting and Control of Nuclear Materials (ABACC) periodic inspections. Because of a number of interests, including financial and/or budgeting situations at the institutions, decades have passed without any further action; the people who originally worked there, and possessed information and knowledge about these facilities, have already moved away from the area, or are in the process of. Therefore, because of the absence of knowledge management techniques in force at the time of establishing and operating these installations, this work proposes an analysis about the possible consequences in case of loss of perhaps the only one remaining knowledge, the one from the people who designed those departments and worked there.