GAIANE SABUNDJIAN

GAIANE SABUNDJIAN

(Fonte: Lattes)

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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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RELAP5 code theoretical simulation of the experiment of natural circulation STAR
2023 - SABUNDJIAN, GAIANE; BELCHIOR JUNIOR, ANTONIO; MAPRELIAN, EDUARDO
Studies have been carried out on nuclear reactors with safety characteristics that do not depend on external intervention by operators or even on an external energy source. In this type of reactors, cooling is carried out by natural circulation, both during normal operation and during shutdown. For this reason, the STAR experiment was built in the IEA-R1 research reactor installed at the Institute for Energy and Nuclear Research (IPEN) – Brazil, with the aim of simulating experiments with the RELAP5 code in order to validate its models in two scenarios: total and partial emptying of the STAR. The results obtained with the RELAP5 code were compared to the experimental ones for the two proposed scenarios. These results showed that the mathematical correlations contained in RELAP5 are capable of reliably and safely reproducing the phenomenology of natural circulation in nuclear reactors.
Uncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant
2018 - BORGES, EDUARDO M.; SABUNDJIAN, GAIANE; DAURIA, FRANCESCO; PETRUZZI, ALESSANDRO
Owing to the occurrence of nuclear accidents, worldwide nuclear regulatory organisations included the analysis of accidents considered as design basis accidents – Loss of Coolant Accident (large and small-break, LBLOCA or SBLOCA) – in the safety analysis reports of nuclear facilities. In Brazil, the tool selected by the licensing authority, Comissão Nacional de Energia Nuclear (CNEN), is RELAP5 Code. The aim of this paper is the evaluation of the performance of the Emergency Core Cooling System (ECCS) of Angra 2 nuclear reactor during SBLOCA. In this study, the RELAP5 code and the Code Internal Assessment of Uncertainty (CIAU) were used to simulate and analyse the uncertainties of the results. The postulated accident is the SBLOCA in the hot leg connected to the ECCS described in the Final Safety Analysis Report of Angra 2 (FSAR/A2). The results from this study were satisfactory when compared with the FSAR/A2.
Proposal for systematic application of BEPU in the licensing process of nuclear power plants
2016 - MENZEL, FRANCINE; SABUNDJIAN, GAIANE; DAURIA, FRANCESCO; MADEIRA, ALZIRA A.
In general, Best Estimate Plus Uncertainty (BEPU) methodology implies application of ‘realistic’ or the so-called ‘best estimate’ computational codes with uncertainty quantification to the thermal-hydraulic safety analyses of nuclear power plants within the licensing process. The results of such analyses are documented in Chapter 15 of Final Safety Analysis Report (FSAR). The objective of the present work is to discuss the possibility of adopting BEPU methodology to the entire FSAR, therefore extending its application range to the other chapters. To perform an entire FSAR based on BEPU, a homogenisation of the analysis is proposed. The first step towards BEPU-FSAR requires identification and characterisation of the parts where numerical analyses are needed (the so-called BEPU topics). The next step is to create a list of key technological areas, the so-called key disciplines and their related key topics and then an overview of the currently computational activities in each technological area. Based on the finalised BEPU applications one can conclude that this methodology is feasible, which encourages to extended its range of use to the other technological areas of FSAR, and therefore to demonstrate the industrial worth and interest. The future step of this work will mainly be focused on the propagation of this expertise into the remaining technical areas of FSAR, adding new knowledge and therefore creating coherent and rigorous background of the BEPU-FSAR methodology.
Web-based post-processor for RELAP5: a development based on LabVIEW
2012 - MACEDO, L.A.; TORRES, W.M.; SABUNDJIAN, G.; ANDRADE, D.A.; BELCHIOR JUNIOR, A.