| Numerical methodology for fluid-structure interaction analysis of nuclear fuel plates under axial flow conditions JG Mantecón, MM Neto Nuclear Engineering and Design 333, 76-86, 2018 | 28 | 2018 |
| Obtainment of hierarchical ZSM-5 zeolites by alkaline treatment for the polyethylene catalytic cracking RB Lima, MMS Neto, DS Oliveira, AGD Santos, LD Souza, VPS Caldeira Advanced Powder Technology 32 (2), 515-523, 2021 | 27 | 2021 |
| Stress corrosion cracking OF Aly, MM Neto Developments in Corrosion Protection, 65-79, 2014 | 14 | 2014 |
| ASME stress linearization and classification-a discussion based on a case study CAJ Miranda, AA Faloppa, M Mattar Neto, G Fainer | 10 | 2011 |
| Options for the interim storage of IEA-R1 research reactor spent fuels AT Silva, MM Neto, RP Mourao, LL Silva, CC Lopes, MCC Silva Progress in Nuclear Energy 50 (7), 836-844, 2008 | 10 | 2008 |
| Modelling of primary water stress corrosion cracking (PWSCC) at control rod drive mechanism (CRDM) nozzles of pressurized water reactors (PWR) OF Aly, AHP Andrade, MM Neto, M Szajnbok, HJ Toth Environment-Induced Cracking of Materials, 143-151, 2008 | 10 | 2008 |
| Numerical analysis on stability of nuclear fuel plates with inlet support comb JG Mantecón, MM Neto Nuclear engineering and Design 342, 240-248, 2019 | 9 | 2019 |
| Analysis and design of spent fuel transport cask impact limiters R Saliba, RP Mourao, F Quintana, O Novara, LL da Silva, CAJ Miranda, ... Packaging, Transport, Storage & Security of Radioactive Material 22 (4), 172-178, 2011 | 7 | 2011 |
| Flow velocity calculation to avoid instability in a typical research reactor core CA Oliveira, M Mattar Neto | 7 | 2011 |
| The use of castor oil polyurethane foam in impact limiters for radioactive materials packages RP Mourao, MM Neto International Journal of Radioactive Materials Transport 14 (1), 49-62, 2003 | 7 | 2003 |
| A methodology for modeling stress corrosion cracking with an example OF Aly, MM Neto, M Schvartzman Proceedings… COBEM-Brazilian Congress of Mechanical Engineering 21, 2011 | 6 | 2011 |
| Preliminary study for extension and improvement on modeling of primary water stress corrosion cracking at control rod drive mechanism nozzles of pressurized water reactors OF Aly, MM Mattar Neto, MM Schvartzman | 6 | 2009 |
| Numerical investigation on the effects of geometric deviations and materials properties on flow-induced deflections of fuel plates JG Mantecón, MM Neto Annals of Nuclear Energy 140, 107118, 2020 | 5 | 2020 |
| Simplified CFD model of coolant channels typical of a plate-type fuel element: an exhaustive verification of the simulations JG Mantecón, MM Neto Brazilian Journal of Radiation Sciences 7 (2B (Suppl.)), 2019 | 5 | 2019 |
| Using eddy current NDT to check integrity of TRIGA MARK I fuel rods cladding DA Alencar, SF Silva Jr, M MATTAR NETO Proceedings of the III World TRIGA Users Conference, 2006 | 5 | 2006 |
| On the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems MM Neto, JRB Cruz, RP de Jong Progress in nuclear energy 50 (7), 800-817, 2008 | 4 | 2008 |
| Modeling of tests of primary water stress corrosion cracking of alloy 182 of pressurized water reactor according to EPRI and USNRC recommendations OF ALY, M MATTAR NETO, MMAM SCHVARTZMAN, LIL LIMA Journal of Technology Innovations in Renewable Energy, 2014 | 3 | 2014 |
| RMB experimental program on the hydrodynamical behavior of fuel assemblies WM Torres, PE Umbehaun, MM Neto, A Belchior Jr, RL Freitas Brazilian Journal of Radiation Sciences 8 (3A (Suppl.)), 2020 | 2 | 2020 |
| Particle swarm optimization applied to the nuclear fuel bundle spacer grid spring design VC Leite, R Schirru, MM Neto Nuclear Technology 205 (5), 637-645, 2019 | 2 | 2019 |
| Compared modeling study of primary water stress corrosion cracking at dissimilar weld of alloy 182 of pressurized water nuclear reactor according to hydrogen concentration OF Aly, MM Neto, MMAM Schvartzman, LIL Lima Journal of Disaster Research 10 (4), 641-646, 2015 | 2 | 2015 |
