| A CFD analysis of the flow dynamics of a directly-operated safety relief valve NL Scuro, E Angelo, G Angelo, DA Andrade Nuclear Engineering and Design 328, 321-332, 2018 | 62 | 2018 |
| Historic survey on nuclear merchant ships LO Freire, DA de Andrade Nuclear Engineering and Design 293, 176-186, 2015 | 44 | 2015 |
| Two-phase flow void fraction estimation based on bubble image segmentation using Randomized Hough Transform with Neural Network (RHTN) PLS Serra, PHF Masotti, MS Rocha, DA de Andrade, WM Torres, ... Progress in Nuclear Energy 118, 103133, 2020 | 25 | 2020 |
| Corrigendum to “On applicability of plate and shell heat exchangers for steam generation in naval PWR”[Nuclear Eng. Des. 280 (2014) 619–627] LO Freire, DA de Andrade | 25* | 2015 |
| A numerical and three-dimensional analysis of steady state rectangular natural circulation loop G Angelo, DA Andrade, E Angelo, WM Torres, G Sabundjian, LA Macedo, ... Nuclear engineering and design 244, 61-72, 2012 | 25 | 2012 |
| Classification of natural circulation two-phase flow patterns using fuzzy inference on image analysis RN De Mesquita, PHF Masotti, RML Penha, DA Andrade, G Sabundjian, ... Nuclear engineering and design 250, 592-599, 2012 | 23 | 2012 |
| Two-phase flow bubble detection method applied to natural circulation system using fuzzy image processing RC Bueno, PHF Masotti, JF Justo, DA Andrade, MS Rocha, WM Torres, ... Nuclear Engineering and Design 335, 255-264, 2018 | 22 | 2018 |
| A MTR fuel element flow distribution measurement preliminary results WM Torres, PE Umbehaun, DA Andrade, JAB Souza | 22 | 2003 |
| Characterization of polyacrylonitrile thermal stabilization process for carbon fiber production using intelligent algorithms BM Terra, DA de Andrade, RN de Mesquita Polymer Testing 100, 107238, 2021 | 16 | 2021 |
| Psychometric model for safety culture assessment in nuclear research facilities CS Do Nascimento, DA Andrade, RN De Mesquita Nuclear Engineering and Design 314, 227-237, 2017 | 16 | 2017 |
| Comparison between experimental data and numerical modeling for the natural circulation phenomenon G Sabundjian, DA Andrade, PE Umbehaun, WM Torres, LA Macedo, ... Journal of the Brazilian Society of Mechanical Sciences and Engineering 33 …, 2011 | 16 | 2011 |
| Preliminary survey on cold fusion: It’s not pathological science and may require revision of nuclear theory LO Freire, DA de Andrade Journal of Electroanalytical Chemistry 903, 115871, 2021 | 12 | 2021 |
| Economically feasible mobile nuclear power plant for merchant ships and remote clients L Ondir Freire, DA de Andrade Nuclear Technology 205 (6), 766-780, 2019 | 10 | 2019 |
| Classification of natural circulation two-phase flow image patterns based on self-organizing maps of full frame DCT coefficients RN de Mesquita, LF Castro, WM Torres, MS Rocha, PE Umbehaun, ... Nuclear Engineering and Design 335, 161-171, 2018 | 10 | 2018 |
| CNEN in the IRIS Project ACO BARROSO, BD BAPTISTA FILHO, ET PALMIERI, G SABUNDJIAN, ... | 10 | 2002 |
| Procedures for manufacturing an instrumented nuclear fuel element M Durazzo, PE Umbehaun, WM Torres, JAB Souza, DG Silva, ... Progress in Nuclear Energy 113, 166-174, 2019 | 9 | 2019 |
| Qualificação a nível transiente da nodalização a2nb03c: Acidente de SBLOCA de 380 cm2 da linha do sistema de resfriamento de emergência do núcleo (SREN), conectada à perna quente DA Andrade, G Sabundjian P&D. CENT. CENT 5, 2001 | 9 | 2001 |
| Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification PE Umbehaun, WM Torres, JAB Souza, M Yamaguchi, AT e Silva, ... World Journal of Nuclear Science and Technology 8 (02), 54, 2018 | 8 | 2018 |
| Development of a VBA macro-based spreadsheet application for RELAP5 data post-processing A Belchior Junior, DA Andrade, G Sabundjian, LA Macedo, G Angelo, ... | 8 | 2011 |
| The Role of Nuclear Power from a System Engineering Standpoint LO Freire, DA de Andrade World Journal of Nuclear Science and Technology 7 (3), 167-188, 2017 | 7 | 2017 |
