GABRIEL ANGELO
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Artigo IPEN-doc 26385 Preliminary numerical analysis of the flow distribution in the core of a research reactor2019 - SCURO, NIKOLAS L.; ANGELO, GABRIEL; ANGELO, E.; TORRES, WALMIR M.; UMBEHAUN, PEDRO E.; ANDRADE, DELVONEI A. deThe thermal-hydraulic safety analysis of research reactors establishes the safety criteria to ensure the integrity of the fuel elements in the reactor core. It assures that all core components are being adequately cooled during operation. It is necessary to know if the average mass flow rate (and their standard deviation) among the fuel assemblies are enough to cool the power generated during operation. Once satisfied such condition, it allows the calculation of the maximum heat flux transferred from fuel assemblies to the coolant, and if the maximum cladding temperatures are below the limits set by the safety criteria. Among the objectives, this study presents a methodology for a preliminary three-dimensional numerical analysis of the flow distribution in the core of the IEA-R1 research reactor, under steady state condition. For this, the ANSYS-CFX® commercial code was used to analyze the flow dynamics in the core, and to visualize the velocity field. It was possible to conclude that a homogeneous flow distribution for all standard fuel assemblies were found, with 2.7% deviation from the average mass flow. What turned out to be negligible and can be assumed that there is a homogeneous distribution in the core. Complex structures were find in the computational domain. Once known the core flow dynamics, it allows future studies to determine whether the heat flux and temperature conditions abbeys thermal-hydraulic safety criteria.Resumo IPEN-doc 24614 A CFD numerical model for the flow distribution in a MTR fuel element2017 - ANDRADE, D.A.; ANGELOA, G.; ANGELO, E.; SANTOS, P.H.G.; OLIVEIRA, F.B.V.; TORRES, W.M.; UMBEHAUN, P.E.; SOUZA, J.A.B.; BELCHIOR JUNIOR, A.; SABUNDJIAN, G.; PRADO, A.C.Previously, an instrumented dummy fuel element (DMPV-01), with the same geometric characteristics of a MTR fuel element, was designed and constructed for pressure drop and flow distribution measurement experiments at the IEA-R1 reactor core. This dummy element was also used to measure the flow distribution among the rectangular flow channels formed by element fuel plates. A CFD numerical model was developed to complement the studies. This work presents the proposed CFD model as well as a comparison between numerical and experimental results of flow rate distribution among the internal flow channels. Numerical results show that the model reproduces the experiments very well and can be used for the studies as a more convenient and complementary tool.Artigo IPEN-doc 20980 A CFD numerical model for the flow distribution in a MTR fuel element2015 - ANDRADE, DELVONEI A. de; ANGELO, GABRIEL; ANGELO, EDVALDO; SANTOS, PEDRO H. di G.; OLIVEIRA, FABIO B.V. de; TORRES, WALMIR M.; EMBEHAUN, PEDRO E.; SOUZA, JOSE A.B. de; BELCHIOR JUNIOR, ANTONIO; SABUNDJIAN, GAIANE; PRADO, ADELK de C.Artigo IPEN-doc 16134 Assessmnet of a heat exchanger inlet nozzle flow using ANSYS-CFX2010 - ANDRADE, DELVONEI A. de; ANGELO, GABRIEL; FAINER, GERSON; ANGELO, EDVALDOAs computational fluid mechanics training task, a preliminary model was developed using ANSYS-CFX. This model was used to provide a better understanding of the heat exchanger inlet nozzle flow of the IEA-R1 nuclear reactor. It was published in the International Nuclear Atlantic Conference-INAC-2009. Now we present a new model with no simplifications for the geometry. Results are presented and discussed.Artigo IPEN-doc 15303 Nuclear research reactor IEA-R1 heat exchanger inlet nozzle flow - a preliminary study2009 - ANGELO, GABRIEL; ANDRADE, DELVONEI A. de; FAINER, GERSON; ANGELO, EDVALDOArtigo IPEN-doc 16968 A CFD model for the IEA-R1 reactor heat exchanger inlet nozzle flow2011 - ANDRADE, DELVONEI A.; ANGELO, GABRIEL; FAINER, GERSON; ANGELO, EDVALDO; UMBEHAUN, PEDRO E.; TORRES, WALMIR M.; SABUNDJIAN, GAIANE; MACEDO, LUIZ A.; BELCHIOR JUNIOR, ANTONIO; CONTI, THADEU N.; WATANABE, BRUNO C.; SAKAI, CAIO C.