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)

Projetos de Pesquisa
Unidades Organizacionais
Cargo

Resultados de Busca

Agora exibindo 1 - 1 de 1
  • 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.