Follow
Nathália Nunes Araújo
Nathália Nunes Araújo
LabRisco, USP, São Paulo
Verified email at labrisco.usp.br
Title
Cited by
Cited by
Year
Unmitigated severe accident analysis for a PWR using MELCOR
NN Araújo, MR Gual, MC Maturana, MR Martins
Progress in Nuclear Energy 128, 103461, 2020
32020
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
32015
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
12017
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
12015
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
The system can't perform the operation now. Try again later.
Articles 1–17