MIGUEL MATTAR NETO
ORCID 
ScopusID 
ResearcherID 
Google Scholar Resumo
Possui graduação em Engenharia Civil pela EPUSP (1977), mestrado em Tecnologia Nuclear pela Universidade de São Paulo (1980) e doutorado em Engenharia Civil - Estruturas pela EPUSP (1991). Atualmente é professor e orientador de Mestrado e Doutorado na área de Tecnologia Nuclear - Reatores da Universidade de São Paulo , consultor de empresas de projeto e fabricantes em projeto mecânico e estrutural de vasos de pressão e tubulações, e tecnologista senior da Comissão Nacional de Energia Nuclear. Tem mais de 30 anos de experiência na área de Engenharia Estrutural, com ênfase em avaliação estrutural e avaliação de integridade estrutural de componentes mecânicos, atuando principalmente nos seguintes temas: vasos de pressão, análise estrutural, método dos elementos finitos, integridade estrutural e análise de tensões. (Texto extraído do Currículo Lattes em 17 nov. 2021)
Lattes 
Orientações 
Projetos Projetos de Pesquisa
Unidades Organizacionais
Cargo
262 resultados
Resultados de Busca
Agora exibindo 1 - 10 de 262
Artigo IPEN-doc 31168 Pressure vessels structural integrity assessment using Failure Analysis Diagrams2025 - PINTO, J.J.R.; MATTAR NETO, M.There is much discussion today about the possibility of extending the lifetime of industrial plant components due to economic factors. Pressure vessels are among the most expensive components, and their replacement can significantly impact the operation of an entire plant. In this context, several Fitness-for-Service (FFS) methodologies can be applied to assess structural integrity, addressing not only economic aspects but also enhancing safety. Failure Assessment Diagrams (FADs) are widely used in FFS methodologies to prevent future failures by analyzing crack-type defects. These diagrams establish acceptability criteria based on the material toughness ratio and loading ratio. Recommended practices utilizing the BS-7910, API-579, and R6 methodologies are addressed in this work, alongside principles from fracture mechanics, material properties, and solid mechanics. The main objective was to develop computer programs in Matlab to analyze a case study involving a pressure vessel manufactured from SA-516 Gr 70 steel, determining the critical dimensions of semi-elliptical cracks in longitudinal and circumferential orientations of a cylindrical section. Level 2 evaluation, the most commonly used in FFS methodologies, was applied to develop the programs. This study enabled the creation of tools to automate calculations and generate FAD graphs, considering the critical depth and length of cracks. These tools support decision-making in structural design requirements and provide a means of evaluating equipment in service with crack-type defects, extending its operational lifetime. The FFS methodologies studied are based on ASME Codes for pressure vessels and piping, particularly Sections III and XI. Based on the analysis of API-579, BS-7910, and R6 methodologies under the operating conditions of the case study, it is possible to conclude that, for normal evaluations, critical length (2c) = 40.64 mm and critical depth (a) = 10.16 mm are acceptable values. However, for evaluations requiring safety considerations under the R6 procedure, applicable to Class A service equipment in the nuclear sector, only critical length (l) = 5 mm and depth (a) = 2.5 mm are permissible values.Artigo IPEN-doc 31166 Study on the licensing framework for land facilities supporting nuclear-powered submarines in the United Kingdom2024 - BARONI, D.B.; BORSOI, S.S.; SOARES, Y.S.A.; MATTAR NETO, M.; OLIVEIRA, P.S.P.; MATURANA, M.C.This study examines nuclear regulation in the United Kingdom, focusing on licensing processes for land facilities supporting nuclear-powered submarines. It highlights the importance of these submarines for defense and maritime security, along with the need for specialized infrastructure to operate them safely and effectively. The study analyzes the UK’s procedures and regulations for nuclear licensing, with emphasis on regulatory bodies such as the Office for Nuclear Regulation (ONR) and the Defence Nuclear Safety Regulator (DNSR). Results discuss the classification of nuclear facilities in the UK, including those dedicated to submarines and nuclear defense, as well as the applicable standards and guidelines for licensing these facilities. It is concluded that nuclear regulation in the UK is robust and transparent, providing a solid foundation for licensing facilities supporting nuclear-powered submarines. The adoption of these standards as a reference in Brazil could significantly contribute to establishing a solid and secure regulatory framework for such facilities.Relatório IPEN-doc 31020 Avaliação do documento LBGN-CP-CEM-NDC-00204 Crane PR01 Calculation Note2025 - MATTAR NETO, MIGUELAvaliação do documento LBGN-CP-CEM-NDC-00204 Crane PR01 Calculation Note.Resumo IPEN-doc 30991 Correlations of mechanical properties by SPT and conventional tensile test for stainless steel 316L2024 - LOBO, RAQUEL de M.; MIRANDA, CARLOS A. de J.; FALOPPA, ALTAIR A.; LIMA, JOSE R. de; MATTAR NETO, MIGUEL; CAJA, FERNANDOThe Small Punch Test (SPT) method is an “almost non-destructive”[1] method by uses miniaturized samples to obtain mechanical properties of materials. It was development by nuclear industry to analyses mechanical behavior of irradiated materials principally by small volume of the samples, which facilitates their storage and handling. Its applications are spreading across several areas of materials engineering, for use in situations where conventional methods do not apply. SPT consists of pressing a sphere, with a diameter equal to 2.5 mm, in a miniaturized sample of circular geometry (diameter d = 8 mm and thickness about 0.5 mm)[2], which has fixed edges, tested in conventional mechanical testing machines with the aid of a device developed for their achievement. In this work, mechanical properties of stainless steel (316 L) were abstained by two different methods: conventional tensile test and the small punch test (SPT), for comparing the results and allow the evaluation of the method. The SPT results depends on graph interpretations and discussions take place at now. Correlations of results guide us in choosing the most appropriated method for interpreting the force x displacement graph from SPT.Relatório IPEN-doc 30924 Relatório IPEN-doc 30923 Relatório IPEN-doc 30922 Relatório IPEN-doc 30921 Avaliação do documento R11.99-9104-EP0400_2 – Geral do LABGENE – Especificação técnica de pintura de equipamentos, estruturas e tubulações2024 - MATTAR NETO, MIGUEL; FALOPPA, ALTAIR A.Relatório IPEN-doc 30920 Relatório IPEN-doc 30919 Avaliação do documento R11.01-2141-BT0400_0 – Critérios básicos de projeto e análise de tensões em tubulações de classe de segurança CS-1 do LABGENE2024 - MATTAR NETO, MIGUEL; FALOPPA, ALTAIR A.