ROBERTO NAVARRO DE MESQUITA

ROBERTO NAVARRO DE MESQUITA

(Fonte: Lattes)

Resumo

Possui graduação em Física pela Universidade Estadual de Campinas (1987), mestrado em Física pela Universidade Estadual de Campinas (1991) e doutorado em Engenharia Mecânica pela Universidade de São Paulo (2002). Atualmente é tecnologista pleno da Comissão Nacional de Energia Nuclear. Tem experiência na área de Ciência da Computação, com ênfase em Sistemas de Inteligência Artificial, atuando principalmente nos seguintes temas: inteligência artificial, diagnóstico de defeitos em tubos, correntes parasitas (ECT), reconhecimento de padrões em imagens. (Texto extraído do Currículo Lattes em 27 dez. 2021)

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Heat transfer mode in the core of the Angra 2 nuclear power plant during small break loca obtained with RELAP5 code
2013 - 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.
Characterization of physical properties of Alsub(2)Osub(3) and ZrOsub(2) nanofluids for heat transfer applications
2015 - ROCHA, MARCELO S.; CABRAL, EDUARDO L.L.; SABUNDJIAN, GAIANE; YORIYAZ, HELIO; LIMA, ANA C.S.; BELCHIOR JUNIOR, ANTONIO; PRADO, ADELK C.; MADI FILHO, TUFIC; ANDRADE, DELVONEI A.; SHORTO, JULIAN M.B.; MESQUITA, ROBERTO N.; OTUBO, LARISSA; BAPTISTA FILHO, BENEDITO D.; PINHO, PRISCILA G.M.; RIBATSKY, GHERHARDT; MORAES, ANDERSON A.U. de
Thermophysical characterization of Alsub(2)Osub(3) and ZrOsub(2) nanofluids as emergency cooling fluids of future generations of nuclear reactors
2015 - ROCHA, MARCELO S.; CABRAL, EDUARDO L.L.; SABUNDJIAN, GAIANE; YORIYAZ, HELIO; LIMA, ANA C.S.; BELCHIOR JUNIOR, ANTONIO; PRADO, ADELK C.; MADI FILHO, TUFIC; ANDRADE, DELVONEI A.; SHORTO, JULIAN M.B.; MESQUITA, ROBERTO N.; OTUBO, LARISSA; BAPTISTA FILHO, BENEDITO D.; RIBATSKY, GHERHARDT; MORAES, ANDERSON A.U. de
ANGRA 2 samll break loca flow regime identification through RELAP5 code
2012 - 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.
The behaviour of ANGRA 2 nuclear power plant core for a small break LOCA simulated with RELAP5 code
2012 - SABUNDJIAN, GAIANE; ANDRADE, DELVONEI A.; BELCHIOR JUNIOR, ANTONIO; ROCHA, MARCELO da S.; CONTI, THADEU das N.; TORRES, WALMIR M.; UMBEHAUN, PEDRO E.; MESQUITA, ROBERTO N.; MASOTTI, PAULO H.F.
Flow regime identification in natural circulation phenomenon using RELAP5 code
2012 - SABUNDJIAN, GAIANE; BELCHIOR JUNIOR, ANTONIO; MESQUITA, ROBERTO N.; MASOTTI, PAULO H.F.; ANDRADE, DELVONEI A.; TORRES, WALMIR M.; UMBEHAUN, PEDRO E.; CONTI, THADEU das N.; ANGELO, GABRIEL
Perspectives of heat transfer enhancements in nuclear reactors toward nanofluids applications
2013 - ROCHA, MARCELO S.; CABRAL, EDUARDO L.L.; SABUNDJIAN, GAIANE; YORIYAZ, HELIO; LIMA, ANA C.S.; BELCHIOR JUNIOR, ANTONIO; PRADO, ADELK C.; MADI FILHO, TUFIC; ANDRADE, DELVONEI A.; SHORTO, JULIAN M.B.; MESQUITA, ROBERTO N.; SOUZA, FRANCISCO A.; OTUBO, LARISSA; BAPTISTA FILHO, BENEDITO D.
The behavior of ANGRA 2 nuclear power plant core for a small break LOCA simulated with RELAP5 code
2013 - 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.
A RELAP5 study to identify flow regime in natural circulation phenomenon
2011 - SABUNDJIAN, GAIANE; TORRES, WALMIR M.; MACEDO, LUIZ A.; MESQUITA, ROBERTO N.; ANDRADE, DELVONEI A.; UMBEHAUN, PEDRO E.; CONTI, THADEU N.; MASOTTI, PAULO H.F.; BELCHIOR JUNIOR, ANTONIO; ANGELO, GABRIEL
Development of a labview web-based simulator for RELAP5
2011 - MACEDO, LUIZ A.; TORRES, WALMIR M.; SABUNDJIAN, GAIANE; ANDRADE, DELVONEI A.; BELCHIOR JUNIOR, ANTONIO; UMBEHAUN, PEDRO E.; CONTI, THADEU N.; MESQUITA, ROBERTO N. de; MASOTTI, PAULO H.F.; ANGELO, GABRIEL