JOSE ANTONIO SENEDA

JOSE ANTONIO SENEDA

(Fonte: Lattes)

Resumo

Possui Doutorado em Tecnologia Nuclear pela Universidade de São Paulo (2006). Atualmente é Professor Colaborador do Instituto de Pesquisas Energéticas e Nucleares-CNEN/SP. Tem experiência na área de Engenharia Química e Nuclear, atuando principalmente em P&D&E de processos de troca iônica para separação, recuperação e descontaminação de Urânio, Tório e Terras Raras, além de Energias Renováveis com alinhamento em Gestão de Risco destas áreas.(Texto extraído do Currículo Lattes em 14 out. 2021)

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Mathematical simulation and technical feasibility of floating solar systems installation in hydroelectric power reservoirs
2024 - PASSOS, RUBENS de O.; SENEDA, JOSE A.; ORTIZ, NILCE
The paper presents a feasibility study for the hybrid system operation of a hydroelectric power plant and a floating photovoltaic plant. Using the database of government agencies, the daily production of electrical energy and the corresponding water flow of the Ilha Solteira hydroelectric power plant in São Paulo, Brazil. The PVsyst software simulated the potential of 480 MWp of a floating photovoltaic plant in the hydroelectric power plant lake. The MATLAB software performed the mathematical modeling, analyzing 12 scenarios of weather conditions on hybrid electricity generation between the hydroelectric power plant (HPP) and the floating photovoltaic plant. The data obtained in the analyzed scenarios show an average monthly reduction of 6% in hydroelectric generation and 7% in the volume of water in the turbine, allowing the generation of electric energy from a floating photovoltaic plant and improving the reserves of water-energy stock, reducing the production of greenhouse gases (GHGs), and avoiding the emission of 55,000 tCO₂ year-1. The financial evaluation shows a cost of US$ 0.73 Wp-1, and 13 years for the floating photovoltaic plant system to start producing a profit. Yet the FPVP is advantageous because it shares the power transmission system of the hydroelectric plant (HPP), and it is not necessary to acquire large land areas.
Must nuclear energy be increased on Brazilian energy mix in a Post-COVID-19 world?
2022 - FERRARI, L.A.; AYOUB, J.M.S.; TAVARES, R.L.A.; SILVA, A.L.C.; SENEDA, J.A.
This paper aims to discuss the convenience and feasibility of increasing the nuclear energy participation on the Brazilian energy mix, amid a national context of climate change, scarcity of natural resources necessary to baseload energy generation, particularly hydropower, discussions on a possible restart and expansion of Brazilian nuclear program, whilst the population still suffers socioeconomic impacts resulting from COVID-19 pandemic as well as the pre-pandemic economic crisis. The work proposes four analysis axes: environmental factors, economic, safety/legislation and technological aspects, and through bibliographic research in scientific articles published in journals, theses, dissertations, laws, regulations and international recommendations, it was possible, as a result of the research, to draw an optimistic overview of a possible future expansion of the Brazilian nuclear program, considering the advantages and challenges of using the nuclear alternative when compared to other energy sources.
Energy and Covid 19
2022 - FERRARI, L.A.; LIMA, L.M.P.R.; RODRIGUES, E.A.; PEREIRA, M.A.M.G.; LIMA, M.; PERINI, E.A.; AYOUB, J.M.S.; SENEDA, J.A.
Pandemics reverberated their times, changing social and economic contexts, prompting, and redirecting changes in social ties, business, and education, restructuring the world that generated them. In this context, this study aims to assess the impact of the COVID-19 pandemic on the global energy matrix, supported by an analysis of consumption, demand, and GDP from January 2019 to June 2021. The energy balance showed variations in this period, with impacts on the environment. We will assess whether the changes will be lasting.
Use o thorium in the generation IV monten salt reactors and perspectives for Brazil
2014 - SENEDA, JOSE A.; LAINETTI, PAULO E.O.
Pure cerium dioxide preparation for use as spectrochemical standard and analysed by inductively coupled plasma mass spectrometry (SF ICP-MS)
2005 - QUEIROZ, C.A.S.; PEDREIRA, W.R.; ABRAO, A.; ROCHA, S.M.R.; VASCONCELLOS, M.E.; SENEDA, J.A.; FORBICINI, C.A.L.G.O.; BOAVENTURA, G.R.; PIMENTEL, M.M.
Recovery of uranium from the filtrate of 'ammonium diuranate' prepared from uranium hexafluoride
2001 - SENEDA, J.A.; FIGUEIREDO, F.F.; ABRAO, A.; CARVALHO, F.M.S.; FRAJNDLICH, E.U.C.
The hydrolysis of uranium hexafluoride and its conversion to 'ammonium diuranate' yields an alkaline solution containing ammonium fluoride and low concentrations of uranium. The recovery of the uranium has the advantage of saving this valuable metal and the avoidance of unacceptable discarding the above mentioned solution to the environment. The recovery of uranium(VI) is based on its complex with the excess of fluoride in the solution and its adsorption on to an anionic ion-exchange resin. The 'ammonium diuranate' filtrate has an approximate concentration of 130 mg l-1 of uranium and 20 g l-1 of ammonium fluoride. An effective separation and recovery of the uranyl fluoride was achieved by choosing a suitable pH and flow rate of the uranium-bearing solution on to the resin column. The effluent ammonium fluoride will be recovered as well. Uranium fluoride adsorbed by the ion-exchanger is then transformed into the corresponding uranyl tricarbonate complex by percolation of a dilute ammonium carbonate solution. Finally, the free fluoride uranium carbonate is eluted from the resin with a more concentrate ammonium carbonate solution. The eluate now can be storage to be precipitated as ammonium uranyl carbonate (AUC). The loading and elution of uranium(VI) on to the ion-exchange column was followed up by a fluorescence test. A flux prepared using a mixture of sodium and potassium carbonate and ammonium fluoride was used for the uranium fluorescence test (ultraviolet lamp). Based on the successful recovery of the uranium on a laboratory scale this process is being considered for use with enriched uranium.
Produção de lantânio de alta pureza para aplicação em P&D
2002 - VASCONCELLOS, M.E.; QUEIROZ, C.A.S.; ROCHA, S.M.R.; SENEDA, J.A.; PEDREIRA FILHO, W.R.; SARKIS, J.E.S.; FORBICINI, C.A.L.G.O.; ABRAO, A.
Descreve-se aqui um procedimento simples e econômico para a obtenção de óxido de lantânio de alta pureza para ser usado como padrão espectroquímico a partir de carbonatos mistos de terras raras provenientes da monazita brasileira. A unidade de produção compõe-se de 4 colunas de acrílico de 3 m de altura e 12 cm de diâmetro, conectadas em série, cada uma preenchida com resina catiônica forte, com capacidade para até 5 kg de óxidos de terras raras/batelada. No processo de separação utiliza-se como eluente uma solução de EDT A-amoniacal em pH 4,0, sem a utilização de qualquer ion retentor. Uma única operação em batelada garante La2O3 ≥ 99,9%. Deu-se grande ênfase ao controle analítico do processo, usando-se a técnica de espectrometria de massa com plasma induzido para a certificação do grau de pureza do material. Foram obtidos, em média, os seguintes resultados para as outras terras raras, no óxido de lantânio, em μg g(-1), respectivamente: Sc (47,01), Y (0,08), Ce (21,61), Pr (0,96), Nd (12,98), Sm (5,86), Eu (0,46), Gd (96,61), Tb (1,43), Dy (0,39), Ho (0,08), Er (0,43), Tm (0,05), Yb (6,48) e Lu (0,06).
Synthesis and thermoanalytical characterization of samarium peroxocarbonate
2004 - QUEIROZ, C.A.S.; VASCONCELLOS, M.E.; ROCHA, S.M.R.; SENEDA, J.A.; PEDREIRA, W.R.; MATOS, J.R.; ABRAO, A.
Primary standardization of sup(72)Ga
2006 - KOSKINAS, MARINA F.; MOREIRA, DENISE S.; TAKEDA, MAURO N.; SENEDA, JOSE A.; DIAS, MAURO da S.
The activity of 72Ga sources produced by irradiation at the IEA-R1 reactor have been performed in a 4 π β - γ coincidence system by using the extrapolation technique. The measurements were undertaken selecting two windows in the γ-channel, in order to check the consistency of the results. A Monte Carlo calculation was performed in order to predict the behavior of the observed activity as a function of the 4πβ detector efficiency and the results were compared to experimental values. © 2006 Elsevier Ltd. All rights reserved.
Study on radiogenic lead recovery from residues in thorium facilities using ion exchange and electrochemical process
2010 - SENEDA, J.A.; FORBICINI, C.A.L.G. de O.; QUEIROZ, C.A. da S.; VASCONCELLOS, M.E. de; FORBICINI, S.; RIZZO, S.M. da R.; SALVADOR, VERA L.R.; ABRÃO, A.
Brazil has one of the biggest mineral thorium reserves, enabling the use of this material in its nuclear reactors. Consequently, this cycle of the fuel would need an initial purification stage of the natural thorium, generating residues from chemical treatment. This work provides operational parameters for the recovery of existing values in these residues, especially the radiogenic lead, that is a radioisotope of thorium decay chain, using ionic exchange technique associated to the electrochemical one. The treatment by ionic exchange in anionic resin and hydrochloric acid medium, provides about 33.4% of radiogenic lead. At the electrochemical process, lead was reduced to a metal in nitric acid medium, presenting a recovery of 98%. The electrochemical process presents an increase in the cost, nevertheless the technological importance of the radiogenic lead in the production of new elements, besides being a strategic material, justifies its use.