GAIANE SABUNDJIAN

Resumo

Possui graduação em Bacharel e Licenciatura Em Física pela Pontifícia Universidade Católica de São Paulo(1978), mestrado em Tecnologia Nuclear / Reatores de Potência pelo Instituto de Pesquisas Energéticas e Nucleares(1981) e doutorado em Engenharia Mecânica pela Escola Politêcnica de São Paulo(1999). Atualmente é TECNOLOGISTA SENIOR do Comissão Nacional de Energia Nuclear. Tem experiência na área de Engenharia Nuclear, com ênfase em Tecnologia dos Reatores. Atuando principalmente nos seguintes temas:Elementos Finitos, Formulação Petrov-Galerkin, Equações de Navier-Stokes, Fluidos Incompressíveis, Funções de Expansão Hierárquicas. (Texto extraído do Currículo Lattes em 13 out. 2021)

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Agora exibindo 1 - 10 de 54
  • Artigo IPEN-doc 26920
    Levantamento bibliográfico sobre metodologias para elaboração de um banco de dados da saúde da população em casos de ocorrências de câncer
    2015 - CAVINATO, C.C.; ANDRADE, D.A.; DIZ, M.D.P.E.; SABUNDJIAN, G.
    As fontes alternativas de energia, incluindo a nuclear, apresentam vantagens com relação às externalidades, as quais podem ser identificadas e relacionadas com o termo, custo ambiental. Este termo, por sua vez, é uma externalidade negativa, que de alguma forma prejudica o meio ambiente e é convertida em termos econômicos, para então poder ser comparada aos demais custos de uma ação e/ou empreendimento. A fim de efetuar os cálculos em questão, são utilizados alguns softwares específicos, os quais possibilitam a conversão dos danos em termos econômicos e a inclusão do custo ambiental na análise de custo de determinado projeto. Uma das dificuldades encontradas na utilização destes softwares tem sido com relação a alguns dados de entrada, como por exemplo, os relativos à saúde da população em torno da instalação nuclear, que são muito deficientes. O objetivo deste trabalho é fazer um levantamento teórico correspondente às metodologias existentes e utilizadas para a elaboração de banco de dados de saúde pública no Brasil. A partir das metodologias encontradas para a formação deste tipo de banco de dados, posteriormente será desenvolvida uma metodologia focando na saúde (câncer fatal e não fatal) da população circunvizinha a uma instalação nuclear, para fins de cálculo do custo ambiental da mesma. Essa será aplicada ao público interno do Instituto de Pesquisas Energéticas e Nucleares (IPEN), como um pré-teste, para aquisição das informações de saúde desejadas.
  • Artigo IPEN-doc 24758
    Classification of natural circulation two-phase flow image patterns based on self-organizing maps of full frame DCT coefficients
    2018 - MESQUITA, ROBERTO N. de; CASTRO, LEONARDO F.; TORRES, WALMIR M.; ROCHA, MARCELO da S.; UMBEHAUN, PEDRO E.; ANDRADE, DELVONEI A.; SABUNDJIAN, GAIANE; MASOTTI, PAULO H.F.
    Many of the recent nuclear power plant projects use natural circulation as heat removal mechanism. The accuracy of heat transfer parameters estimation has been improved through models that require precise prediction of two-phase flow pattern transitions. Image patterns of natural circulation instabilities were used to construct an automated classification system based on Self-Organizing Maps (SOMs). The system is used to investigate the more appropriate image features to obtain classification success. An efficient automated classification system based on image features can enable better and faster experimental procedures on two-phase flow phenomena studies. A comparison with a previous fuzzy inference study was foreseen to obtain classification power improvements. In the present work, frequency domain image features were used to characterize three different natural circulation two-phase flow instability stages to serve as input to a SOM clustering algorithm. Full-Frame Discrete Cosine Transform (FFDCT) coefficients were obtained for 32 image samples for each instability stage and were organized as input database for SOM training. A systematic training/test methodology was used to verify the classification method. Image database was obtained from two-phase flow experiments performed on the Natural Circulation Facility (NCF) at Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN), Brazil. A mean right classification rate of 88.75% was obtained for SOMs trained with 50% of database. A mean right classificationrate of 93.98% was obtained for SOMs trained with 75% of data. These mean rates were obtained through 1000 different randomly sampled training data. FFDCT proved to be a very efficient and compact image feature to improve image-based classification systems. Fuzzy inference showed to be more flexible and able to adapt to simpler statistical features from only one image profile. FFDCT features resulted in more precise results when applied to a SOM neural network, though had to be applied to the full original grayscale matrix for all flow images to be classified.
  • Resumo IPEN-doc 24614
    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.
  • Resumo IPEN-doc 23885
    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.
  • Artigo IPEN-doc 21153
    Casos de cancer fatal e não fatal ocorridos nas diferentes regiões do municipio de São Paulo
    2015 - ANDRADE, TATIANE T.L.; CAVINATO, CHRISTIANNE C.; ANDRADE, DELVONEI A.; SABUNDJIAN, GAIANE
  • Artigo IPEN-doc 21137
    Characterization of physical properties of Alsub(2)Osub(3) and ZrOsub(2) nanofluids for heat transfer applications
    2015 - ROCHA, MARCELO S.; CABRAL, EDUARDO L.L.; SABUNDJIAN, GAIANE; YORIYAZ, HELIO; LIMA, ANA C.S.; BELCHIOR JUNIOR, ANTONIO; PRADO, ADELK C.; MADI FILHO, TUFIC; ANDRADE, DELVONEI A.; SHORTO, JULIAN M.B.; MESQUITA, ROBERTO N.; OTUBO, LARISSA; BAPTISTA FILHO, BENEDITO D.; PINHO, PRISCILA G.M.; RIBATSKY, GHERHARDT; MORAES, ANDERSON A.U. de
  • Artigo IPEN-doc 21082
    Simulation of the first step of the coupling of the PARCS/RELAP5 codes to ANGRA 2 facility
    2015 - POZZO, ANDREA S. del; ANDRADE, DELVONEI A. de; SABUNDJIAN, GAIANE
  • Artigo IPEN-doc 21073
    Self-organizing maps applied to two-phase flow on natural circulation loop studies
    2015 - CASTRO, LEONARDO F.; CUNHA, KELLY de P.; ANDRADE, DELVONEI A. de; SABUNDJIAN, GAIANE; TORRES, WALMIR M.; MACEDO, LUIZ A.; ROCHA, MARCELO da S.; MASOTTI, PAULO H.F.; MESQUITA, ROBERTO N. de
  • Artigo IPEN-doc 20980
    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.
  • Artigo IPEN-doc 20797
    Thermophysical characterization of Alsub(2)Osub(3) and ZrOsub(2) nanofluids as emergency cooling fluids of future generations of nuclear reactors
    2015 - ROCHA, MARCELO S.; CABRAL, EDUARDO L.L.; SABUNDJIAN, GAIANE; YORIYAZ, HELIO; LIMA, ANA C.S.; BELCHIOR JUNIOR, ANTONIO; PRADO, ADELK C.; MADI FILHO, TUFIC; ANDRADE, DELVONEI A.; SHORTO, JULIAN M.B.; MESQUITA, ROBERTO N.; OTUBO, LARISSA; BAPTISTA FILHO, BENEDITO D.; RIBATSKY, GHERHARDT; MORAES, ANDERSON A.U. de