EDUARDO MADEIRA BORGES

EDUARDO MADEIRA BORGES

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Análise do acidente de perda de refrigerante primário devido a quebra da linha de surto do pressurizador da usina nuclear Angra 2
2020 - BORGES, EDUARDO M.; CONTI, THADEU das N.; SANCHES, ANDREA; SABUNDJIAN, GAIANE
O objetivo deste trabalho foi simular e avaliar com o código RELAP5 o acidente base de projeto de perda de refrigerante primário devido a uma ruptura média na linha de surto do pressurizador da usina nuclear Angra 2. Este acidente foi uma quebra do tipo guilhotina ou seja 100% na linha de surto do pressurizador, que representa uma ruptura de 437 cm². Nesta análise, verificou-se que as lógicas de atuação do Sistema de Proteção do Reator (SPR) e do Sistema de Resfriamento de Emergência do Núcleo (SREN) de Angra 2, utilizadas nesta simulação, funcionaram corretamente, mantendo a integridade do núcleo com as temperaturas do núcleo em níveis aceitáveis durante todo o evento. Os resultados obtidos foram satisfatórios, quando comparados com os apresentados no Relatório Final de Análise de Segurança de Angra 2 (FSAR/A2).
Small break loss of coolant accident of 200 cm² in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
2019 - BORGES, EDUARDO M.; SABUNDJIAN, GAIANE
The aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 200cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for ANGRA 2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core.
RELAP5 code simulation of the small break loss of coolant accident of 80 cm² in the cold leg of Angra2 primary loop
2019 - BORGES, EDUARDO M.; SABUNDJIAN, GAIANE; BRAZ FILHO, FRANCISCO A.; GUIMARÃES, LAMARTINE N.F.
The aim of this paper was to simulate and evaluate the basic design accident of 80 cm² small break loss of coolant accident (SBLOCA) in the cold leg of the primary loop of the Angra2 nuclear power plant. In this simulation, it was verified that the actuation logics of the Angra2 Reactor Protection System (RPS) and the Emergency Core Cooling System (ECCS) used in this simulation worked correctly, maintaining core integrity with acceptable temperatures throughout the event. The results obtained were satisfactory when compared with those presented by the Angra2 Final Safety Analysis Report (FSAR/A2).
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.
Identification of flow regimes and heat transfer modes in ANGRA2 core during the simulation of the small break loss of coolant accident of 250 cm2 in the cold leg of primary loop using RELAP5 code
2017 - BORGES, EDUARDO M.; SABUNDJIAN, GAIANE
The aim of this paper is to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 250cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for Angra2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core.
Flow regimes and heat transfer modes identification in ANGRA 2 core, during small break in the primary loop with area of 100 cmsup(2), simulated with RELAP5 code
2015 - BORGES, EDUARDO M.; SABUNDJIAN, GAIANE
Comparison between experimental data and numerical modeling for the natural circulation phenomenon
2009 - SABUNDJIAN, GAIANE; ANDRADE, DELVONEI A.; UMBEHAUN, PEDRO E.; TORRES, WALMIR M.; MACEDO, LUIZ A.; CONTI, THADEU N.; MESQUITA, ROBERTO N.; MASOTTI, PAULO H.F.; PENHA, ROSANI M.L.; SILVA FILHO, MAURO F.; MELO, GABRIEL R.; BRAZ FILHO, FRANCISCO A.; BORGES, EDUARDO M.
Verification and validation of one dimensional models used in subcooled flow boiling analysis
2009 - BRAZ FILHO, FRANCISCO A.; CALDEIRA, ALEXANDRE D.; BORGES, EDUARDO M.; SABUNDJIAN, GAIANE