Miguel Mattar Neto
TítuloCitado porAno
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
82008
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, N Mattar, M Miguel, MM Schvartzman
62009
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
62008
Using Eddy Current NDT to Check Integrity of TRIGA MARK I Fuel Rods Cladding
DA Alencar, SFS Junior, MM Neto
NDT. net-The e-Journal of Nondestructive Testing (October 2008), 2006
62006
Stress corrosion cracking
OF Aly, MM Neto
Developments in Corrosion Protection, 2014
52014
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
52011
ASME stress linearization and classification-a discussion based on a case study
CAJ Miranda, AA Faloppa, N Mattar, G Fainer
42011
Proposition of theoretical improvement on models of primary water stress corrosion cracking
OF Aly, MM Neto
Tecnologia em Metalurgia, Materiais e Mineracao 20100726, 300-308, 2010
42010
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
32008
Modeling of primary water stress corrosion cracking at control rod drive mechanism nozzles of pressurized water reactors
OF Aly, AHP de Andrade, MM Neto, MMAM Schvartzman
Modelagem da fratura por corrosão sob tensão em mecanismo de acionamento das …, 2006
32006
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
32003
Modeling of Tests of Primary Water Stress Corrosion Cracking of Alloy 182 of Pressurized Water Reactor According to EPRI and USNRC Recommendations
OF Aly, MM Neto, MMAM Schvartzman, LIL Lima
Journal of Technology Innovations in Renewable Energy 3 (4), 214-220, 2014
22014
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
22011
Flow velocity calculation to avoid instability in a typical research reactor core
CA Oliveira, N Mattar
22011
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 Neto, AHP de Andrade, M Schvartzman
64th ABM Annual Congress, 2009
22009
Fatigue test plan to obtain SN curves
JMA Pinto, EA Colosimo, TR Mansur, JRB Cruz, ES Palma, MM Neto
ASME 2002 Pressure Vessels and Piping Conference, 201-204, 2002
22002
Fatigue test plan to obtain SN curves
JMA Pinto, EA Colosimo, TR Mansur, JRB Cruz, ES Palma, MM Neto
ASME 2002 Pressure Vessels and Piping Conference, 201-204, 2002
22002
Interpreting ASME limits and philosophy in FEA of pressure vessel parts
LM Bezerra, JRB Cruz, CAJ Miranda, MM Neto
International pressure vessels and piping codes and standards. Volume 2 …, 1995
21995
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
12018
Finite Element Cold Bending Residual Stress Evaluation on Submarine Pressure Hull Instability Assessment
PR Franquetto, MM Neto
Journal of Offshore Mechanics and Arctic Engineering 138 (6), 061101, 2016
12016
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