MARCELO DA SILVA ROCHA

MARCELO DA SILVA ROCHA

(Fonte: Lattes)

Resumo

Possui graduação em Engenharia Civil pela Universidade Federal de Juiz de Fora (1996), mestrado em Engenharia Civil pela Universidade Estadual de Campinas (1998) e doutorado em Engenharia Mecânica pela Universidade de São Paulo (2005). Realizou estágio de pós-doutorado em Engenharia Mecânica na Universidade de São Paulo (2007) e em Engenharia Nuclear no Instituto de Pesquisas Energéticas e Nucleares (2009). Atualmente é Pesquisador Adjunto do Centro de Engenharia Nuclear (CEENG) do Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN). Atua como docente e pesquisador nas áreas de termohidráulica de reatores, energias renováveis, interação fluido-estrutura e aplicações de nanotecnologia. (Texto extraído do Currículo Lattes em 16 nov. 2021)

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CFD Simulation of isothermal upward two-phase flow in a vertical annulus using interfacial area transport equation
2023 - CERAVOLO, FLAVIO E.; ROCHA, MARCELO da S.; MESQUITA, ROBERTO N. de; ANDRADE, DELVONEI A. de
This work presents a numerical simulation of a vertical, upward, isothermal two-phase flow of air bubbles and water in an annular channel applying a Computational Fluid Dynamics (CFD) code. For this, the Two-Fluid model is applied considering interfacial force correlations, namely: drag, lift, wall lubrication, turbulent dispersion, and virtual mass. The turbulence k-ε model effects and the influence of One-group Interfacial Area Transport Equation (IATE) are taken into account, in this case, the influence of two source term correlations for the bubble breakup and coalescence IATE is analysed. The work assesses whether the code properly represents the physical phenomenon by comparing the simulation results with experimental data obtained from the literature. Six flow conditions are evaluated based on two superficial liquid velocities and three void fractions in the bubbly flow regimen. The annular channel adopted has an outer pipe with an internal diameter of 38.1 mm and an inner cylinder of 19.1 mm. To represent this geometry, a three-dimensional mesh was generated with 160,000 elements, after a mesh sensitivity study. The void fraction distribution, taken radially to the flow section, is the main parameter analysed as well as interfacial area concentration, interfacial gas velocity, and bubble sizes distribution. The CFD model implemented in this work demonstrates satisfactory agreement with the reference experimental data but indicates the need for further improvement in the phase interaction models.
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.