LUIZ ALBERTO MACEDO
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Resumo IPEN-doc 24578 Experiments of loss of coolant in the IEA-R1 reactor2017 - MAPRELIAN, E.; TORRES, W.M.; BELCHIOR JUNIOR, A.; UMBEHAUN, P.E.; SANTOS, S.C.; FRANÇA, R.L.; PRADO, A.C.; MACEDO, L.A.; SILVA, A.T. E; BERRETTA, J.R.; SABUNDJIAN, G.The Loss of Coolant Accident (LOCA) has been considered Design Basis Accident (DBA) for several kind of reactors. The test section for experimental (STAR) for simulation of LOCA, using the Instrumented Fuel Assembly (IFA) EC-208 was designed, assembled, commissioned, and used for the experiments at the IEA-R1 Reactor. The experiments were performed for five different levels of fuel uncovering and two heat decay conditions. The five levels consisted of one total and four partial uncovering of the IFA. The results obtained for each experiment were the section level and 13 IFA temperatures. A data acquisition system was used to record the process parameters. The STAR section has proved to be a very safe and efficient tool for fuel uncovering experiments to obtain thermal-hydraulic data for research and development, and for the data to be compared with safety analysis code calculations.Resumo IPEN-doc 23885 Heat transfer mode in the core of the Angra 2 nuclear power plant during small break loca obtained with RELAP5 code2013 - SABUNDJIAN, GAIANE; BELCHIOR JUNIOR, ANTONIO; CONTI, THADEU das N.; ROCHA, MARCELO da S.; ANDRADE, DELVONEI A. de; TORRES, WALMIR M.; MACEDO, LUIZ A.; UMBEHAUN, PEDRO E.; MESQUITA, ROBERTO N. de; LIMA, ANA C. de S.This work aims to identify the heat transfer mode with RELAP5/MOD3.2.gama code in the core of Angra 2 facility. The postulate accident is the Loss of Coolant Accident (LOCA) in the primary circuit for Small Break (SB), which is described in Chapter 15 of the Final Safety Analysis Report of Angra 2 (FSAR). The accident consists basically of the total break of the cold leg of Angra 2 facility. The rupture area considered was 380 cm2, which represents 100% of the primary circuit pipe °ow area. The Emergency Core Cooling System (ECCS) e±ciency is also tested in this accident. In this simulation, failure and repair criteria are adopted for the ECCS components in order to verify the system operation e±ciency - preserving the integrity of the reactor core and guaranteeing its cooling - as expected by the project design. SBLOCA accidents are characterized by a fast blowdown in the primary circuit to values that activate the low pressure injection system followed by the water injection from the accumulators. The thermal-hydraulic processes inherent to the accident phenomenon, such as hot leg vaporization and consequently core vaporization cause inappropriate °ow distribution in the reactor core that can lead to reduction in the core liquid level, up to the point that the ECCS is able to re°ood it. This work shows the mode numbers and the wall convection heat transfer used in the RELAP5 code that were accessed during the execution of the program. The results showed that the numerical simulations with RELAP5 were satisfactory and that the ECCS worked e±ciently, guaranteeing the integrity of the reactor core.Artigo IPEN-doc 21115 Commissioning of the star test section for experimental simulation of loss coolant accident using the EC-208 instrumented fuel assembly of the IEA-R1 reactor2015 - MAPRELIAN, EDUARDO; TORRES, WALMIR M.; PRADO, ADELK C.; UMBEHAUN, PEDRO E.; FRANÇA, RENATO L.; SANTOS, SAMUEL C.; MACEDO, LUIZ A.; SABUNDJIAN, GAIANEArtigo IPEN-doc 21073 Self-organizing maps applied to two-phase flow on natural circulation loop studies2015 - CASTRO, LEONARDO F.; CUNHA, KELLY de P.; ANDRADE, DELVONEI A. de; SABUNDJIAN, GAIANE; TORRES, WALMIR M.; MACEDO, LUIZ A.; ROCHA, MARCELO da S.; MASOTTI, PAULO H.F.; MESQUITA, ROBERTO N. deArtigo IPEN-doc 16135 Study of the natural circulation phenomenon for nuclear reactors2010 - CONTI, THADEU das N.; SABUNDJIAN, GAIANE; TORRES, WALMIR M.; MACEDO, LUIZ A.; ANDRADE, DELVONEI A.; UMBEHAUN, PEDRO E.; MESQUITA, ROBERTO N.Artigo IPEN-doc 16126 Analise teorico/experimental do fenomeno de circulacao natural2010 - SABUNDJIAN, GAIANE; CONTI, THADEU N.; TORRES, WALMIR M.; MACEDO, LUIZ A.; ANDRADE, DELVONEI A.; UMBEHAUN, PEDRO E.; MESQUITA, ROBERTO N.; SILVA FILHO, MAURO F.; BRAZ FILHO, FRANCISCO A.; BORGES, EDUARDO M.Artigo IPEN-doc 16127 Thermal hydraulic phenomenology in a natural circulation circuit2010 - TORRES, WALMIR M.; MACEDO, LUIZ A.; MESQUITA, ROBERTO N.; MASOTTI, PAULO H.F.; SABUNDJIAN, GAIANE; ANDRADE, DELVONEI A.; UMBEHAUN, PEDRO E.Artigo IPEN-doc 18514 ANGRA 2 samll break loca flow regime identification through RELAP5 code2012 - ROCHA, MARCELO da S.; SABUNDJIAN, GAIANE; BELCHIOR JUNIOR, ANTONIO; ANDRADE, DELVONEI A. de; TORRES, WALMIR M.; CONTI, THADEU das N.; MACEDO, LUIZ A.; UMBEHAUN, PEDRO N.; MESQUITA, ROBERTO N. de; MASOTTI, PAULO H.F.Artigo IPEN-doc 08710 Controle de sistemas passivos em circulacao natural por meio de linhas de desvio2002 - BAPTISTA FILHO, B.D.; MACEDO, L.A.Artigo IPEN-doc 19812 The behavior of ANGRA 2 nuclear power plant core for a small break LOCA simulated with RELAP5 code2013 - SABUNDJIAN, GAIANE; ANDRADE, DELVONEI A.; BELCHIOR JUNIOR, ANTONIO; ROCHA, MARCELO da S.; CONTI, THADEU N.; TORRES, WALMIR M.; MACEDO, LUIZ A.; UMBEHAUN, PEDRO E.; MESQUITA, ROBERTO N.; MASOTTI, PAULO H.F.; LIMA, ANA C. de S.