PEDRO HENRIQUE DI GIOVANNI SANTOS

PEDRO HENRIQUE DI GIOVANNI SANTOS

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RANS-based CFD calculation for pressure drop and mass flow rate distribution in an MTR fuel assembly
2021 - SCURO, N.L.; ANGELO, G.; ANGELO, E.; UMBEHAUN, P.E.; TORRES, W.M.; SANTOS, P.H.G.; FREIRE, L.O.; ANDRADE, D.A.
This work presents a Reynolds-averaged Navier Stokes–based computational fluid dynamics methodology for the calculation of pressure drop and mass flow rate distribution in a material test reactor flat-plate-type standard fuel assembly (SFA) of the IEA-R1 Brazilian research reactor to predict future improvements in newer SFA designs. The results improve the understanding of the origin of fuel plate oxidation due to high temperatures, and consequently, due to the internal flow dynamics. All numerical analyses were performed with the ANSYS-CFX® commercial code. The observed results show that the movement pin decreases the central channel mass flow due to the length of the vortex at the inlet region. However, the outlet nozzle showed greater general influence in the flow dynamics. It should have a more gradual cross-section transition being away from the fuel plates or a squarer-shaped design to get a more homogeneous mass flow distribution. Optimizing both regions could lead to a better cooling condition. The validation of the IEA-R1 numerical methodology was made by comparing the McMaster University’s dummy model experiment with a numerical model that uses the same numerical methodology. The experimental data were obtained with laser Doppler velocimetry, and the comparison showed good agreement for both pressure drop and mass flow rate distribution using the Standard k-ω turbulence model.
Modelagem numérica de um elemento combustível para estudos hidrodinâmicos
2018 - SANTOS, PEDRO H. di G.
É visível, no mundo atual, a elevada dependência da utilização de energia elétrica. Na tentativa de suprir as necessidades de consumo e impedir o déficit energético, a sociedade faz uso dos mais diversos artifícios para a obtenção desta. Nesta perspectiva, a utilização da energia nuclear vem sempre sendo recolocada nos fóruns mundiais de geração elétrica revelando-se uma alternativa eficiente, limpa e de baixo custo. Devido à complexidade enfrentada durante a instalação de empreendimentos nucleares diversos protocolos, equipamentos e ações de segurança são empregados para garantir a operação segura da planta nuclear ao longo de sua vida útil. Reatores de pesquisas prestam suporte no desenvolvimento de novas tecnologias e práticas de segurança, desde que estes tenham seus fenômenos e comportamentos bem compreendidos como base de partida. O presente trabalho destina-se a criar suporte para a atualização da análise de segurança do reator de pesquisa IEA-R1. Testes numéricos foram conduzidos para validar a viabilidade de construção de um modelo computacional capaz de apresentar resultados similares aos dados experimentais já existentes. O trabalho mostra que a distribuição de vazão no elemento combustível ocorre de forma não uniforme com os canais laterais recebendo vazões menores do que os centrais. Os canais periféricos recebem uma vazão média de 95% da vazão principal enquanto os canais centrais recebem até 105% da vazão principal. Os resultados são ligeiramente diferentes dos resultados experimentais apresentados anteriormente, entretanto apresentam uma boa correlação com outros estudos numéricos em elementos combustíveis similares.
Transient cfd analysis of the flow inversion of the nuclear research reactor IEA-R1
2018 - SCURO, N.L.; SANTOS, P.G.; UMBEHAUN, P.E.; ANDRADE, D.A.; ANGELO, E.; ANGELO, G.
The IEA-R1 research reactor works with a downflow direction, but after pumps shutdown during a LOFA test, the reactor shutdown. The heat decay will be removed by natural convection, which is an upward flow, originating flow inversion. Using the Instrumented Fuel Element designed at the Institute for Energy and Nuclear Research (IPEN), the loss of flow accident (LOFA) was analyzed along instrumented fuel plates. The preliminary results showed temperature peaks during inversion, which is as much representative as in nominal operation at 3.5MW. Therefore, these experimental data lead a construction and validation of a transient three-dimensional numerical analysis for a single fuel channel using the ANSYS-CFX® commercial code. The numerical results show improvement in obtaining more properties, e.g., wall heat transfer coefficient, which is usually obtained through empirical correlations.
A CFD numerical model for the flow distribution in a MTR fuel element
2017 - 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.
Numerical study of the influence of elements inside the wheelhouse on the passenger vehicle aerodynamic
2015 - ANGELO, EDVALDO; ANGELO, GABRIEL; SANTOS, PEDRO H. di G.; ANDRADE, DELVONEI A. de
A CFD numerical model for the flow distribution in a MTR fuel element
2015 - 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.