THADEU DAS NEVES CONTI

THADEU DAS NEVES CONTI

(Fonte: Lattes)

Resumo

Has graduation at Física (Bacharelado) by Pontifícia Universidade Católica de São Paulo (1979) , master's at Tecnologia Nuclear by Universidade de São Paulo (1983) and Ph.D. at Engenharia Mecânica by Universidade de São Paulo (2006) . Currently is of Comissão Nacional de Energia Nuclear, Livre of Universidade de São Paulo, Membro de comitê assessor of (FAPESP) Fundação de Amparo à Pesquisa do Estado de São Paulo, Membro de comitê assessor of Comissão Nacional de Energia Nuclear, Revisor de periódico of Revista Internacional de Ciências e Revisor de periódico of Revista Ciência, Tecnologia & Ambiente. Has experience in the area of Nuclear Engineering , with emphasis on Combustível Nuclear. Focused, mainly, in the subjects: Simulação Numérica, Modelagem Matemática, Escoamento Bifásico. (Text obtained from the Currículo Lattes on November 29th 2021)

Possui graduação em Física (Bacharelado) pela Pontifícia Universidade Católica de São Paulo(1979), mestrado em Tecnologia Nuclear pela Universidade de São Paulo(1983) e doutorado em Engenharia Mecânica pela Universidade de São Paulo(2006). Atualmente é Pesquisador do Comissão Nacional de Energia Nuclear, Professor da Pós Graduação da Universidade de São Paulo, Membro de comitê assessor da (FAPESP) Fundação de Amparo à Pesquisa do Estado de São Paulo, Membro de comitê assessor do Comissão Nacional de Energia Nuclear, Revisor de periódico da Revista Internacional de Ciências e Revisor de periódico da Revista Ciência, Tecnologia & Ambiente. Tem experiência na área de Engenharia Nuclear, com ênfase em Combustível Nuclear. Atuando principalmente nos seguintes temas:Simulação Numérica, Modelagem Matemática, Escoamento Bifásico. (Texto extraído do Currículo Lattes em 29 nov. 2021)

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Increasing the effectiveness of the security system on a nuclear facility
2017 - VAZ, A.C.A.; CONTI, T.N.; ANDRADE, D.A.
The malicious use of radioactive material could be devastating, particularly in the case of a nuclear explosive device, it could be unpredictably disruptive resulting in the dispersal of radioactive material, like it was in the Fukushima Daiichi Nuclear Power Plant disaster. Physical Protection System (PPS) plays an important role in ensuring that individuals, organizations and institutions remain vigilant and that sustained measures are taken to prevent and combat the threat of sabotage or of using radioactive material for malicious acts. PPS is an integrated system of people, equipment and procedures used to protect nuclear facilities and radioactive sources against threat, theft or sabotage. In the operator’s perspective, this paper study factors influencing the performance of a PPS in a nuclear facility suggesting ways to increase the system effectiveness. The human factor, the physical and the psychological work environment has a large impact on how personnel perform their work and comply with nuclear security requirements. Apathy and corporatism are two human behaviors that collaborate negatively and make decrease the effectiveness of any PPS. Job satisfaction reduces the probability that personnel will become less reliable and/or obstructive in extreme cases an insider threat. Managers must recognize individual and group needs and the relationship among personnel so that they may motivate personnel by creating a supportive working environment that reduces workplace stress. An effective PPS can result in a significant increase in the effectiveness of the security of radioactive material and associated facilities.
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.
Irradiacao de miniplacas de elementos combustiveis tipo dispersao de reatores de pesquisa
2008 - DOMINGOS, DOUGLAS B.; CONTI, THADEU das N.; YAMAGUCHI, MITSUO; SILVA, JOSE E.R. da; ANDRADE, DELVONEI A. de; UMBEHAUN, PEDRO E.; TEIXEIRA e SILVA, ANTONIO
Study of the natural circulation phenomenon for nuclear reactors
2010 - CONTI, THADEU das N.; SABUNDJIAN, GAIANE; TORRES, WALMIR M.; MACEDO, LUIZ A.; ANDRADE, DELVONEI A.; UMBEHAUN, PEDRO E.; MESQUITA, ROBERTO N.
Analise teorico/experimental do fenomeno de circulacao natural
2010 - 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.
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.
Analise teorico e experimental do fenomeno de circulacao natural
2008 - SABUNDJIAN, GAIANE; ANDRADE, DELVONEI A. de; UMBEHAUN, PEDRO E.; TORRES, WALMIR M.; CASTRO, ALFREDO J.A. de; CONTI, THADEU das N.; MASOTTI, PAULO H.F.; MESQUITA, ROBERTO N. de; PALADINO, PATRICIA A.; BRAZ FILHO, FRANCISCO A.; BORGES, EDUARDO M.; BELCHIOR JUNIOR, ANTONIO; ROCHA, RICARDO T.V. da; DAMY, OSVALDO L.A.
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
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.