ALTAIR ANTONIO FALOPPA
6 resultados
Resultados de Busca
Agora exibindo 1 - 6 de 6
Artigo IPEN-doc 29551 IEA-R1 renewed primary system pump B1-B nozzles stress analysis2022 - FALOPPA, A.A.; FAINER, G.; FIGUEIREDO, C.D.R.; CARVALHO, D.S.M.; MATTAR NETO, M.The present report is a summary of the structural analysis of the pump nozzles applying the finite element method by using the Ansys computer program. The IEA-R1 RR is an open pool-type moderated and cooled by light water using beryllium/graphite as a reflector. The reactor can reach up to 5MW of thermal power cooled by the primary and secondary systems. The primary coolant system consists of a piping arrangement, a decay tank, two pumps, and two heat exchangers. The primary pump B1-B presented some failures requiring refurbishment by a new one. The pump used in the IEA-R1 must meet the requirements inherent to the nuclear installation, in addition to the operational requirements for rotating equipment, such as flow and pressure, and structural integrity of the body and nozzles. The supplier specified the type of pump suitable for the System. The pump furnished granted mechanical allowable loads for the nozzles that were lower than the loads imposed by the piping on the nozzles. To enable the installation of the pump in the primary circuit, new support was inserted in the piping system next to the pump minimizing efforts and deformations. A piping stress analysis was carried out to obtain the new efforts imposed on the nozzles. For validation of the motor pump set, a verification of the nozzles was done compared with API 610 standard loads, and the allowable loads of the provider. Finally, a structural analysis of the pump nozzles with the new loads was developed using the finite element method. The calculated stresses meet the limits prescribed by the ASME code; therefore, the new B1-B Pump is approved for operation at the IEA-R1 Nuclear Research Reactor primary circuit.Artigo IPEN-doc 28278 Small punch test devices in development at IPEN aiming to perform tests in RMB hot cells2021 - MIRANDA, C.A.J.; LIMA, J.R.; FALOPPA, A.A.; ANDRADE, A.H.P. de; MATTAR NETO, M.; CASTAGNET, M.; LOBO, R.M.; PEREIRA, L.S.Artigo IPEN-doc 28230 IEAR1 renewed primary system pump B1B nozzles stress analysis2021 - FALOPPA, A.A.; FAINER, G.; FIGUEIREDO, CAROLINA D.R.; CARVALHO, D.S.M.; MATTAR NETO, M.Relatório IPEN-doc 28312 Análise Estrutural Preliminar da Solda Externa do Suporte M242021 - MATTAR NETO, MIGUEL; MIRANDA, CARLOS A. de J.; FALOPPA, ALTAIR A.Artigo IPEN-doc 26370 Structural integrity analysis of the heavy water reflector tanks of the IPEN/MB-01 Reactor2019 - 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, MIGUELThe 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.Artigo IPEN-doc 24028 Structural evaluation of IEA-R1 primary system pump nozzles2017 - FAINER, GERSON; FALOPPA, ALTAIR A.; OLIVEIRA, CARLOS A. de; MATTAR NETO, MIGUELThe 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.