Unmitigated severe accident analysis for a PWR using MELCOR NN Araújo, MR Gual, MC Maturana, MR Martins Progress in Nuclear Energy 128, 103461, 2020 | 3 | 2020 |
Measurement of interfacial parameters of single Taylor bubbles rising in closed vertical and slightly inclined tubes using ultrasonic and visualization techniques MB de Azevedo, D dos Santos, NN Araujo, PAM Vinhas, JLH Faccini, ... CONGRESS OF MECHANICAL ENGINEERING 23, 2015 | 3 | 2015 |
Estudo do Sistema passivo de remoção de calor residual de um reator PWR pequeno modular NN Araujo, JLH Faccini, J Su 2017 International Nuclear Atlantic Conference-INAC, 2017 | 1 | 2017 |
Estudo Experimental Do Movimento De Bolhas Alongadas Individuais Em Tubos Vertical e Ligeiramente Inclinados Usando Uma Tecnica De Visualizacao NN Araújo, PAM Vinhas, MB de Azevedo, JLH Faccini, J Su Proceedings of The International Nuclear Atlantic Conference, Sao Paulo-Brazil, 2015 | 1 | 2015 |
Analysis of hydrogen control in a Small Modular Reactor during TLOFW severe accident MR Gual, MC Maturana, NN Araújo, MR Martins Brazilian Journal of Radiation Sciences 12 (2), e2359-e2359, 2024 | | 2024 |
CFD study of a fLOFA in the IAEA 10 MW generic MTR reactor using a 3D analytical heat source term PPSP Lopes, UAM Neto, MR Gual, NN Araújo, MC Maturana, MR Martins AIP Conference Proceedings 3034 (1), 2024 | | 2024 |
A SWOT analysis of a Floating Nuclear Power Plant for electricity generation in Brazil MR Gual, MC Maturana, HCR Júnior, NN Araújo Brazilian Journal of Radiation Sciences 11 (4), 1-17, 2023 | | 2023 |
Problems in Application of Level 2 Probabilistic Safety Assessment for NPP in Brazil MR Gual, MC Maturana, NN Araújo, HCR Júnior Proceedings of the INAC 2021: international nuclear atlantic conference …, 2021 | | 2021 |
Application of a Level 2 PSA methodology in the event of loss of coolant circulation accident in the spent fuel pool of a vSMR NN Araújo, MR Gual, HC Romberg, MC Maturana, R Martins Marcelo Proceedings of the INAC 2021: international nuclear atlantic conference …, 2021 | | 2021 |
MELCOR steady state calculation of the generic PWR of 40MWth NN Araújo, MC Maturana, MR Gual Brazilian Journal of Radiation Sciences 8 (3A), 2020 | | 2020 |
Modeling LOFW in a PWR using MELCOR MR Gual, MC Maturana, NN Araújo, MR Martins Brazilian Journal of Radiation Sciences 8 (3A (Suppl.)), 2020 | | 2020 |
ANALYTICAL SIMULATION OF A PWR USING MELCOR MR Gual, NN Araújo, MC Maturana Brazilian Journal of Radiation Sciences 8 (3A (Suppl.)), 2020 | | 2020 |
Analytical simulation of a PWR using MELCOR NN Araújo, MC Maturana, MR Gual Proceedings of the INAC 2019: international nuclear atlantic conference …, 2019 | | 2019 |
Análise térmica de um sistema de remoção de calor residual de um reator de pequeno porte NN Araújo Universidade Federal do Rio de Janeiro, 2018 | | 2018 |
Estudo experimental do movimento de bolhas alongadas individuais em tubos vertical e ligeiramente inclinados usando uma técnica de visualização MB Azevedo, JLH Faccini Instituto de Engenharia Nuclear, 2015 | | 2015 |
SPENT FUEL POOL SEVERE ACCIDENTS MODELLED WITH MELCOR TO SUPPORT A PSA LEVEL 2 NN ARAÚJO, MR GUAL, MC MATURANA IAEA TECDOC SERIES, 21, 0 | | |
Study of passive residual heat removal system of a modular small PWR reactor NN Araujo, JLH Faccini, J Su | | |