| Fuzzy methodology applied to probabilistic safety assessment for digital system in nuclear power plants ACF Guimarães, CMF Lapa, M de Lourdes Moreira Nuclear Engineering and Design 241 (9), 3967-3976, 2011 | 52 | 2011 |
| Structural and magnetic properties of nanoparticles of La2/3Sr1/3MnO3 ML Moreira, JM Soares, WM De Azevedo, AR Rodrigues, FLA Machado, ... Physica B: Condensed Matter 384 (1-2), 51-53, 2006 | 24 | 2006 |
| A new finite element formulation for both compressible and nearly incompressible fluid dynamics PAB De Sampaio, ML Moreira International journal for numerical methods in fluids 32 (1), 43-67, 2000 | 17 | 2000 |
| The IRIS pressurizer: Simulation of out-surge transients and optimization procedure to design scaled experiments DA Botelho, PAB De Sampaio, CMF Lapa, CMNA Pereira, ... Progress in Nuclear Energy 50 (7), 730-739, 2008 | 12 | 2008 |
| Temperature Distribution Fuel Rods: A study on the Effect of Eccentricity in the Position of U02 Pellets MML Gaspar Jr, PAB Desampaio 0-th International Conference «Nuclear Energy for New Europe, 2011 | 11 | 2011 |
| Nondeterministic method to analysis of the aging effects in PWR power plants components D da Silva Borges, DD Lava, ACF Guimarães, M de Lourdes Moreira Annals of Nuclear Energy 81, 249-256, 2015 | 8 | 2015 |
| Pontes de concreto armado: efeitos da corrosão e da variação do módulo de elasticidade do concreto PTC Mendes, MLT Moreira, PM Pimenta Revista IBRACON de estruturas e materiais 5, 388-419, 2012 | 7 | 2012 |
| Optimization procedure to design pressurizer experiments DA Botelho, PAB Sampaio, CMF Lapa, CMNA Pereira, ML Moreira, ... Instituto de Engenharia Nuclear, 2005 | 7 | 2005 |
| Reliability study of the auxiliary feed-water system of a pressurized water reactor by faults tree and Bayesian Network DD Lava, DS Borges, ACF Guimarães, ML Moreira | 6 | 2017 |
| Probabilistic safety assessment applied to research reactors ACF Guimarães, ML Moreira Book: Current Research in Nuclear Reactor Technology in Brazil and Worldwide …, 2013 | 6 | 2013 |
| Analysis of Natural Circulation in a Thermal-hydraulic Loop Similar to a Passive Nuclear Reactor Cooling System DA Botelho, JLH Faccini, PAB De Sampaio, ML Moreira RT− IEN 1, 2002 | 6 | 2002 |
| Fractional scaling method applied to a pressurizer test facility DA Botelho, PAB De Sampaio, M de Lourdes Moreira, ACO Barroso Progress in Nuclear Energy 52 (3), 258-267, 2010 | 5 | 2010 |
| Two-phase Natural Circulation Similarity Criteria for Passive Nuclear Reactor Cooling Systems under Normal and Maximum Velocity Conditions DA Botelho, JLH Faccini, PAB De Sampaio, ML Moreira RT− IEN 1, 2002 | 5 | 2002 |
| Monitoreo del avance de la frontera agropecuaria en el Chaco Argentino HR Zerda, ML Moreira Anais do VII Seminario de Atualização em Sensoriamento Remoto e Sistemas de …, 2006 | 4 | 2006 |
| Simulation of IRIS pressurizer out-surge transient using two and three volumes simulation models DA Botelho, PAB Sampaio, ML Moreira, ACO Barroso Instituto de Engenharia Nuclear, 2005 | 4 | 2005 |
| Dynamical interaction between a droplet and a wall heated beyond the Leidenfrost temperature RI Martins, M de Lourdes Moreira, J Su Annals of Nuclear Energy 168, 108910, 2022 | 3 | 2022 |
| Transient 3D heat transfer analysis up to the state of Dryout in fuel rods RI Martins, RRW Affonso, M de Lourdes Moreira, PAB de Sampaio Annals of Nuclear Energy 115, 39-54, 2018 | 3 | 2018 |
| The effect of eccentricity in the position of UO2 pellets PAB DeSampaio, M de Lourdes Moreira, JCA Gaspar Jr Progress in Nuclear Energy 69, 23-28, 2013 | 3 | 2013 |
| Solution of the spatial kinetic equations using the expansion in pseudo-harmonics ZR Lima, FC Silva, ACM Alvim | 3 | 2011 |
| Application of fractional scaling analysis and local scaling to design a test facility of IRIS pressurizer DA Botelho, PAB de Sampaio, M de Lourdes Moreira, ACO Barroso | 3 | 2007 |
Paulo A B De SampaioInstituto de engenharia nuclear, comissão nacional de energia nuclear, ien, cnen, university collegeien.gov.br üzerinde doğrulanmış e-posta adresine sahip
