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)

Página do item completo

Resultados de Busca

Agora exibindo 1 - 10 de 11

Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification
2018 - UMBEHAUN, PEDRO E.; TORRES, WALMIR M.; SOUZA, JOSE A.B.; YAMAGUCHI, MITSUO; SILVA, ANTONIO T. e; MESQUITA, ROBERTO N. de; SCURO, NIKOLAS L.; ANDRADE, DELVONEI A. de
This paper presents the sequence of activities to improve the thermal hydraulic analysis of the IEA-R1 research reactor to operate in safe conditions after power upgrade from 2 to 5 MW and core size reduction from 30 to 24 fuel assemblies. A realistic analysis needs the knowledge of the actual operation conditions (heat flow, flow rates) beyond the geometric data and the uncertainties associated with manufacturing and measures. A dummy fuel assembly was designed and constructed to measure the actual flow rate through the core fuel assemblies and its pressure drop. First results showed that the flow distribution over the core is nearly uniform. Nevertheless, the values are below than the calculated ones and the core bypass flow rate is greater than those estimated previously. Based on this, several activities were performed to identify and reduce the bypass flow, such as reduction of the flow rate through the sample irradiators, closing some unnecessary secondary holes on the matrix plate, improvement in the primary flow rate system and better fit of the core components on the matrix plate. A sub-aquatic visual system was used as an important tool to detect some bypass flow path. After these modifications, the fuel assemblies flow rate increased about 13%. Additional tests using the dummy fuel assembly were carried out to measure the internal flow distribution among the rectangular channels. The results showed that the flow rate through the outer channels is 10% - 15% lower than the internal ones. The flow rate in the channel formed between two adjacent fuel assemblies is an estimated parameter and it is difficult to measure because this is an open channel. A new thermal hydraulic analysis of the outermost plates of the fuel assemblies takes into account all this information. Then, a fuel design modification was proposed with the reduction of 50% in the uranium quantity in the outermost fuel plates. In order to avoid the oxidation of the outermost plates by high temperature, low flow rate, a reduction of 50% in the uranium density in the same ones was shown to be adequate to solve the problem.
Estudos para implantacao de uma instalacao para NCT no reator IEA-R1 do IPEN-CNEN/SP
1996 - FERREIRA, D.B.M.; ZAHN, G.S.; ROGERO, J.R.; MAIORINO, J.R.; DAMY, M.A.; CAMILLO, M.A.P.; NASCIMENTO, N.; COELHO, P.R.P.; PUGLIESI, R.; MESQUITA, R.N.; VIEIRA, W.J.
Self-organizing maps of kohonen (COM) applied to multidimensional monitoring data of the IEA-R1 nuclear research reactor
2011 - AFFONSO, GUSTAVO S.; BUENO, ELAINE I.; PEREIRA, IRACI M.; MESQUITA, ROBERTO N. de
Simulacao dos acidentes de partida a frio e queda de um elemento combustivel no reator IEA-R1m
1999 - RODRIGUES, A.C.I.; TEIXEIRA e SILVA, A.; CABRAL, E.L.L.; MESQUITA, R.N.; CONTI, T.N.
Design of a facility for NCT research in the IEA-R1 reactor
1996 - CAMILLO, M.A.P.; COELHO, P.R.P.; DAMY, M.A.; FERREIRA JUNIOR, D.B.M.; MAIORINO, J.R.; MESQUITA, R.N.; NASCIMENTO, N.; PUGLIESI, R.; ROGERO, J.R.; VIEIRA, W.J.; ZAHN, G.S.
Analise de seguranca do reator IEA-R1 a 5MW
2000 - TEIXEIRA e SILVA, A.; MAPRELIAN, E.; RODRIGUES, A.C.I.; CABRAL, E.L.L.; MOLNARY, L.; MESQUITA, R.N.; MENDONCA, A.G.
A human error probability estimate methodology based on fuzzy inference and expert judgment of nuclear plants
2009 - NASCIMENTO, C.S. do; MESQUITA, R.N. de
Analise de acidentes de insercao de reatividade em reatores de pesquisa do tipo piscina
1996 - RODRIGUES, A.C.I.; SILVA, A.T.; CABRAL, E.L.L.; MESQUITA, R.N.; YAMAGUCHI, M.; GENTA, M.
Analise de acidentes de perda de vazao para o reator IEA-R1m
1997 - MESQUITA, R.N.; CABRAL, E.L.L.; RODRIGUES, A.C.I.
Analise de acidentes de insercao de reatividade postulados para o reator IEA-R1m
1997 - RODRIGUES, A.C.I.; TEIXEIRA e SILVA, A.; CABRAL, E.L.L.; MESQUITA, R.N.