CARLOS ALBERTO DE OLIVEIRA

CARLOS ALBERTO DE OLIVEIRA

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Structural integrity analysis of the heavy water reflector tanks of the IPEN/MB-01 Reactor
2019 - FAINER, GERSON; FALOPPA, ALTAIR A.; OLIVEIRA, CARLOS A. de; JUNQUEIRA, FERNANDO C.; FIGUEIREDO, CAROLINA D.R.; SANTOS, MARCELO M. dos; CARVALHO, DANIEL S.M.; MATTAR NETO, MIGUEL
The IPEN/MB-01 is a zero power research reactor designed and built by IPEN in partnership with the Brazilian Navy. This reactor is located in IPEN and began operating in 1988. IPEN/MB-01 has been used as an experimental facility for studies on neutron parameters of nuclear reactors moderated by light water. In 2016, a project to modify the core structure of IPEN/MB-01 Reactor was initiated. This project aims the replacement of the rod-type fuel structure for a plate-type one. In order to optimize the performance of the experiments, four tanks filled with D2O were installed around the core. This new core will contain fuel elements that are similar to the ones that will be used in the Brazilian Multipurpose Reactor. In this paper, a complete structural integrity analysis of the four heavy water reflector tanks installed in IPEN/MB-01 Reactor is presented. A numerical analysis was performed applying the finite element method, using ANSYS software and considering ASME Code VIII, division 2.
Structural evaluation of IEA-R1 primary system pump nozzles
2017 - FAINER, GERSON; FALOPPA, ALTAIR A.; OLIVEIRA, CARLOS A. de; MATTAR NETO, MIGUEL
The IEA-R1 pumps of the primary coolant system may be required to withstand design and operational conditions. IEA-R1 nuclear research reactor is an open pool type reactor operated by IPEN since 1957. The reactor can be operated up to 5MW heating power since it was upgraded in a modernization program conducted by IPEN. The primary coolant system is composed by the piping system, decay tank, two heat pumps and two heat exchangers. In the latest arrangement upgrade of the primary system, conducted in 2014 as part of an aging management program, a partial replacement of the coolant piping and total replacement of piping and pump supports were done. As consequence, reviewed loads in the pump nozzles were obtained demanding a new evaluation of them. The aim of this report is to present the structural evaluation of the pump nozzles, considering the new loads coming from the new piping layout, according to: API 610 code verification, Supplier loads and structural analysis applying finite element method, by using the ANSYS computer program, regarding ASME VIII Div 1 & 2 recommendations.
Avaliação estrutural de um suporte da tubulação do sistema de refrigeração do reator nuclear de pesquisa IPEN IEA-R1
2016 - FALOPPA, ALTAIR A.; FAINER, GERSON; OLIVEIRA, CARLOS A. de; MATTAR NETO, MIGUEL
Este trabalho apresenta a avaliação estrutural de um suporte da tubulação do Circuito Primário do reator nuclear de pesquisa do Instituto de Pesquisas Energéticas e Nucleares - IPEN. O reator IEA-R1 é um reator nuclear de pesquisa projetado pela Babcox-Wilcox que opera no IPEN desde 1957. Um programa de modernização tem sido conduzido nos últimos 25 anos, e uma série de modificações foram implementadas, especialmente no sistema de refrigeração do reator. Entre as modificações mais recentes está a troca de componentes do sistema de refrigeração, tais como: bombas, trocadores de calor e tubulação, além da reforma dos sistemas de tratamento e re-tratamento de água. Este conjunto de equipamentos, divididos em sistema primário e secundário, é responsável pela circulação da água no núcleo do reator para a retirada de calor gerado pela fissões nucleares do U-235. A substituição parcial da tubulação do Circuito Primário do reator IEA-R1, realizada em 2014, resultou em alterações nos suportes existentes e no desenvolvimento de um novo tipo de suporte para a tubulação. O objetivo deste trabalho é apresentar o modelo de cálculo aplicado à avaliação estrutural deste novo suporte sob as diversas condições de carregamentos aplicáveis.
IEA-R1 renewed primary coolant piping system stress analysis
2015 - FAINER, GERSON; FALOPPA, ALTAIR A.; OLIVEIRA, CARLOS A. de; MATTAR NETO, MIGUEL
Refurbishment of the IEA-R1 primary coolant system piping supports
2015 - FAINER, GERSON; FALOPPA, ALTAIR A.; OLIVEIRA, CARLOS A. de; MATTAR NETO, MIGUEL
Stress analyses of the internals of a research PWR vessel. A general overview
1995 - MIRANDA, C.A.J.; MATTAR NETO, M.; OLIVEIRA, C.A.; CRUZ, J.R.B.; ASSIS, G.M.V.; ALBUQUERQUE, L.B.
Stress analysis of a research PWR pressure vessel. A general description
1995 - MIRANDA, C.A.J.; MATTAR NETO, M.; OLIVEIRA, C.A.; CRUZ, J.R.B.; BEZERRA, L.M.; ALBUQUERQUE, L.B.; ASSIS, G.M.V.
Ageing assessment of the brazilian research reactor IEA-R1 core
2010 - MARCELINO, S.; OLIVEIRA, C.A. de; MATTAR NETO, MIGUEL
IEA-R1 primary and secondary coolant piping systems coupled stress analysis
2013 - FAINER, GERSON; FALOPPA, ALTAIR A.; OLIVEIRA, CARLOS A.; MATTAR NETO, MIGUEL
Analysis framework to calibrate a numerical model to simulate the thermal test of a 1:2 scale dual purpose cask under accident conditions
2013 - MIRANDA, CARLOS A.J.; LIBARDI, ROSANI M.P.; MARCELINO, SERGIO; OLIVEIRA, CARLOS A. de; MATTAR NETO, MIGUEL