Paulo Fernando Ferreira Frutuoso e Melo
Instituição:
Universidade Federal do Rio de Janeiro
Centro:
Centro de Tecnologia
Unidade:
Coordenação dos Programas de Pós-Graduação de Engenharia
Departamento:
Programa de Engenharia Nuclear/COPPE
Formação:
-
Universidade Federal do Rio de Janeiro
Engenharia Nuclear | Doutorado | 1982 - 1993
-
Universidade Federal do Rio de Janeiro
Engenharia Nuclear | Mestrado | 1978 - 1981
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Universidade Federal do Rio de Janeiro
Física | Graduação | 1974 - 1977
Laboratórios:
Nenhum laboratório cadastrado
Nuvens de Palavras:
Artigos:
(47.30% artigos com DOI)
| Titulo | DOI | Ano |
|---|---|---|
| Subsea pipelines incidents prevention: A case study in Brazil | 10.1016/j.jlp.2023.105007 | 2023 |
| Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project | 10.1080/00295450.2022.2155021 | 2023 |
| Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima | 10.1080/00295450.2023.2229182 | 2023 |
| Evaluation of the probability of overflow from the Abadia de Goiás repository by the Fokker-Planck equation using the Trotter?s formula | 10.1016/j.nucengdes.2023.112493 | 2023 |
| How does subsea processing safety policy impact safety? Lessons learned from the Brazilian experience | 10.1016/j.jlp.2021.104668 | 2022 |
| How Risk-Informed Decisions Can Fail: Lessons from a Nuclear Power Plant Incident | 10.1021/acs.chas.1c00039 | 2022 |
| On the viability of wearing evaluation by Thin Layer Activation in the presence of non-occupationally exposed individuals | 10.1007/s41365-022-01012-2 | 2022 |
| Well integrity assessment under uncertainty considerations and evaluation of the workover frequency impact | 10.1007/s40430-022-03482-2 | 2022 |
| Sensitivity analysis of the accident rate of a plant equipped with a protection channel under aging by the generalized perturbation theory | 10.1016/j.anucene.2022.109278 | 2022 |
| A Method for Monitoring and Evaluating the Management of a Nuclear Regulatory Body Using a New Approach for Cross-cutting Indicators | 10.1080/00295450.2022.2050041 | 2022 |
| Decommissioning of Nuclear Submarines and the Interim Storage of Their Reactor Compartments | 10.1115/1.4054385 | 2022 |
| Identification and quantitative analysis of radiological and chemical risks in a uranium isotopic enrichment plant | 10.22533/at.ed.3172222203103 | 2022 |
| Availability assessment of a nuclear reactor limitation system by a Timed Petri Net | 10.1016/j.pnucene.2022.104380 | 2022 |
| The phased application of STAMP, FRAM and RAG as a strategy to improve complex sociotechnical system safety | 10.1016/j.pnucene.2020.103571 | 2021 |
| Application of a quantitative human performance model to the operational procedure design of a fuel storage pool cooling system | 10.1016/j.ress.2021.107989 | 2021 |
| Evaluation of the Accident Rate of a Plant Equipped with an Aging Single Protective Channel by the Method of Supplementary Variables | 10.5540/tcam.2021.022.04.00533 | 2021 |
| How do organizational structures impact operational safety? Part 1 - Understanding the dangers of decentralization | 10.1016/j.ssci.2019.104568 | 2020 |
| How do organizational structures impact operational safety? Part 2 - Designing structures that strengthen safety | 10.1016/j.ssci.2019.104534 | 2020 |
| 3D simulation model of water infiltration for radioactive waste on a virtual reality Environment: An application to the Abadia de Goiás repository | 10.1016/j.anucene.2019.107265 | 2020 |
| Component unavailability model for PSA Level I applications considering aging and startup degradation: An Application to an Emergency Diesel Generator System | 10.1016/j.anucene.2020.108000 | 2020 |
| Análise Qualitativa de Segurança para a Remoção e Transferência de Rejeito Líquido Radioativo em uma Instalação de Apoio em Terra para um Submarino Nuclear | 2019 | |
| A review of the cognitive basis for human reliability analysis | 10.1016/j.pnucene.2019.103050 | 2019 |
| Quantitative Analysis of Integrity Failures in Subsea Oil Wells Using a Markovian Model | 10.2118/198891-pa | 2019 |
| Steady-state Accident Rate of a Plant Equipped with an Aging Single-channel Trip Device | 2018 | |
| A method for the identification of a set of critical safety functions for a uranium hexafluoride conversion plant | 10.1016/j.anucene.2016.01.016 | 2016 |
| Simplification of transition state diagrams via Generalized Perturbation Theory in the Markovian reliability analysis of aging safety systems | 10.1016/j.anucene.2016.03.003 | 2016 |
| Human reliability analysis of the Tokai-Mura accident through a THERP-CREAM and expert opinion auditing approach | 10.1016/j.ssci.2016.04.009 | 2016 |
| A Human Reliability Analysis of Radiotherapy Procedures Using Bayesian Networks and Expert Opinion Elicitation | 2016 | |
| Underground parallel pipelines domino effect: An analysis based on pipeline crater models and historical accidents | 10.1016/j.jlp.2016.05.031 | 2016 |
| Sensitivity analysis of the accident rate of a plant by the generalized perturbation theory | 2016 | |
| Including severe accidents in the design basis of nuclear power plants: An organizational factors perspective after the Fukushima accident | 10.1016/j.anucene.2015.01.016 | 2015 |
| Stochastic and deterministic models to evaluate the critical distance of a near surface repository for the disposal of intermediate and low level radioactive wastes | 10.1016/j.nucengdes.2015.01.020 | 2015 |
| An Itô model of pit corrosion in pipelines for evaluating risk-informed decision making | 10.1016/j.nucengdes.2015.06.026 | 2015 |
| Coupling of a Lumped Parameter and a Finite Difference Model for Estimation of a Reactivity Induced Transient in a PWR with Annular Fuel Rods | 2014 | |
| A DFM/Fuzzy/ATHEANA Human Failure Analysis of a Digital Control System for a Pressurizer | 2014 | |
| Simplification of State Transition Diagrams in Average Unavailability Analysis by Using Generalized Perturbation Theory | 10.1155/2014/242408 | 2014 |
| A Critical Review of Methods and Models for Evaluating Organizational Factors in Human Reliability Analysis | 10.1016/j.pnucene.2014.04.004 | 2014 |
| Análise de Confiabilidade umana como Ferramenta de Gestão | 2014 | |
| Failure Probability Evaluation of a Near-surface Radioactive Waste Repository due to Water Infiltration | 2013 | |
| A THERP/ATHEANA Analysis of the Latent Operator Error in Leaving EFW Valves Closed in the TMI-2 Accident | 10.1155/2013/787196 | 2013 |
| Safety Integrity Level (SIL) Integrated with Human and Organizational Factors | 2013 | |
| A Root Cause Analysis Method for Industrial Plant Reliability Improvement and Engineering Design Feedback | 2013 | |
| On the Impact of Human and Organizational Archetypes on Human Failure Probabilities Used in Risk Analyses | 2013 | |
| Atmospheric Dispersion and Dose Evaluation due to the Fall of a Radioactive Package ata LILW Facility | 2013 | |
| A Human Reliability Analysis of Radiotherapy Procedures Using Bayesian Networks | 2013 | |
| Reliability Attributes and the Maintenance Rule for Nuclear Power Plant Safety System | 2013 | |
| Analysis of the qualified life extension of nuclear safety systems through modulated Poisson point processes | 10.1016/j.pnucene.2012.06.003 | 2012 |
| Risk-Based Allowed Outage Time and Surveillance Test Interval Extensions for Angra 1 | 10.1155/2012/176270 | 2012 |
| A Behavior- and Observation-Based Monitoring Process for Safety Management | 2010 | |
| Aplicação de um Modelo Fuzzy DEA para Priorizar Modos de Falha em Sistemas Nucleares | 2009 | |
| An adaptive management system for hazardous technology | 2007 | |
| An Update of the Probabilistic Safety Assessment of the Radiation Monitor Calibration Laboratoryu of a Brazilian Nuclear Power Station | 2007 | |
| Deterministic and Probabilistic Approaches to Fatigue Crack Growth in Nuclear Pressure Vessels | 2007 | |
| Unavailability analysis of safety systems under aging by supplementary variables with imperfect repair | 2005 | |
| NAROAS: a neural network-based advanced operator support system for the assessment of system reliability | 2005 | |
| Optimización de la Política de Mantenimiento Preventivo del Sistema de Inyección de Alta Presión de un Reator Nuclear Típico Usando un Modelo de Confiabilidad y Costos | 2005 | |
| A Fuzzy Data Envelopment Analysis Approach for FMEA | 2005 | |
| Uma Modelagem Matemática para o Cálculo da Disponibilidade de Componentes de Sistemas | 2005 | |
| Comportamento da Taxa de Falha como Conhecimento Necessário para a Formulação de Hipóteses Estatísticas na Pesquisa de Confiabilidade | 2003 | |
| Surveillance Test Policy Optimization Through Genetic Algorithms Using Non-Periodic Intervention Frequencies and Considering Seasonal Constraints | 2003 | |
| An Application of Genetic Algorithms to Surveillance Tests Optimization of a PWR Auxiliary Feedwater System | 2002 | |
| Avaliação da Disponibilidade dos Sistemas de Refrigeração de Componentes e Geradores Diesel de Emergência de Angra II Considerando Outage Times | 2002 | |
| Safety Culture of Complex Risky Systems: The Nuclear Engineering Institute Case Study | 2002 | |
| An Application of Non-homogeneous Poisson Point Processes to the Reliability Analysis of Service Water Pumps | 2001 | |
| Availability of a Component Subject to an Erlangian Failure Model under Wearout by Supplementary Variables | 1999 | |
| On Probability Models for the Unavailability Analysis of Safety Systems under Aging Phenomena | 1999 | |
| Recent Advances in Perturbative Methods Applied to Nuclear Engineering Problems | 1998 | |
| Sensitivity analysis on the accident rate of a plant equipped with a single protective channel by generalized perturbation methods | 10.1016/s0306-4549(97)00118-7 | 1998 |
| Um Modelo de Manutenção Baseado em Critérios de Dependência Econômica e de Disponibilidade | 1998 | |
| Análisis Markoviano de la Indisponibilidad de un Sistema de Reserva | 1998 | |
| An Application of the Concept of Limiting Expenditures in Risk-Reduction Measures to the Brazilian Case | 1993 | |
| Hazard Rate of a Plant Equipped with a Tw-Channel Protective System Subjet to a High Demand Rate | 1990 | |
| An Initial Appraisal of the Event-Tree Methodology Used in the Angra I Nuclear Power Station Probabilistic Safety Assessment | 1987 | |
| An Application of the Explicit Method for Analysing Intersystem Dependencies in the Evaluation of Event Trees | 1985 |
Eventos:
(3.83% eventos com DOI)
| Titulo | DOI | Ano |
|---|---|---|
| The Role of Physical Parameters on the Overflow Probability of a Radioactive Near Surface Repository for Low & Intermediate Level Wastes: The Case of Abadia de Goi'as | 10.3850/978-981-18-8071-1_P316-cd | 2023 |
| A Methodology Proposal for Estimating the Costs Associated with Failure Effects of Subsea Equipment | 10.3850/978-981-18-8071-1_P270-cd | 2023 |
| Methodology for defining risk indices applicable to subsea equipment | 2022 | |
| Component Criticality Rating of a Subsea Manifold using FMECA | 10.3850/981-973-0000-00-0_esrel2022-paper | 2022 |
| Reactivity Sensitivity Analysis for a Fuel Rod with Biconcave Cross Section in a PWR | 10.3850/978-981-11-2724-3_0676-cd | 2019 |
| Determination of Maximum Water Temperature within the Spent Fuel Pool of Angra Nuclear Power Plant - Unit 3 | 2017 | |
| Ana¿lise de Sensibilidade da Taxa de Acidente de uma Planta Industrial por Cadeias de Markov e Teoria de Perturbac¿a¿o Generalizada (GPT) | 10.5540/03.2017.005.01.0190 | 2017 |
| Accident rate of a plant equipped with an aging single-channel trip device with non-exponential demand and repair times | 10.1063/1.4982023 | 2017 |
| A Monte Carlo evaluation of the accident rate of a plant equipped with an aging single-channel trip device | 10.1063/1.4992743 | 2017 |
| Análise Qualitativa de Segurança para a Remoção e Transferência de Rejeito Líquido Radioativo em uma Instalação de Apoio em Terra para um Submarino de Propulsão Nuclear | 2017 | |
| Modelagem Markoviana para a Análise de Confiabilidade de um Poço de Petróleo | 2017 | |
| Simulation of Inadvertent Rod Cluster Control Assembly Bank Withdrawal at Power for Angra 1 NPP Using an LQR Digital Controller | 2015 | |
| An Initial Uncertainty Analysis on the Critical Heat Flux Evaluation for a Small-Scale Pressurized Nuclear Water Reactor Using the COBRA Code | 2015 | |
| Human-Machine Interface (HMI) scenario quantification performed by ATHEANA, A Technique for Human Error Analysis | 2015 | |
| On the Simulation of Transients and Accidents in PWRs with Digital Instrumentation and Control Using an LQR Digital Conroller | 2015 | |
| Considerations about the Licesing Process of Special Nuclear Industrial Facilities | 2015 | |
| Unavailability of the Residual Heat Removal System of Angra 1 by Bayesian Networks Considering Dependent Events | 2015 | |
| Methodology for System Reliability Analysis During the Conceptual Phase of Complex System Design Considering Human Factors | 2015 | |
| Risk-Informed Approach in Nuclear Power Plants: Brazilian Experience | 2015 | |
| Automation Performance to Get Situation and Automation Awareness in Human-System Interface Design: A Discussion on the State of the Art | 2015 | |
| Uma Proposta de Abordagem para a Identificação de Fatores de Desempenho (PSFs) em Instalações Nucleares | 2015 | |
| Human Reliability Analysis through a Bayesian Network using Expert Opinion and an Auditing Tool: An Application to the Tokai-Mura Accident | 2015 | |
| Cold Water Injection and Rod Ejection Analysis of Annular Fueled PWRs by a Hybrid Lumped Parameter Model | 2014 | |
| Application of the maintenance rule to nuclear power plant systems through Bayesian networks | 2014 | |
| Experience on risk-informed approach to allowed outage time changes due to planned maintenance | 2014 | |
| An Expert Elicitation and Bayesian Network Approach for Human Reliability Analysis of Radiotherapy Procedures | 2013 | |
| A Socio-technical Approach to Quantify Human Failure Probabilities | 2013 | |
| A Lumped Parameter Finite Difference Model for Analyzing Reactivity Induced Transients in a PWR with Annular Fuel Rods | 2013 | |
| Modelo Estocástico para o Estudo do Transbordamento de um Repositório Próximo à Superfície para a Deposição de Rejeitos Radioativos de Baixo e Médio Níveis de Radiação | 2013 | |
| Sobre a Aplicabilidade de Funções Críticas de Segurança a uma Unidade de Conversão de Hexafluoreto de Urânio | 2013 | |
| Evaluation of Radiological Risk Curves for Liquid Radioactive Waste Transfer from Angra 1 to Angra 2 Nuclear Power Plants by a Container Tank | 2013 | |
| On the Risk-Informed Evaluation Approach to Nuclear Power Plant Technical Specifications Change | 2013 | |
| Root-Cause Analysis as a Tool for Industrial Plant Reliability Improvement and Engineering Design Feedback | 2013 | |
| A Proposal of Safety Indicators Focused on Human and Organizational Factors | 2013 | |
| A Comparison Between Markovian Models and Bayesian Networks for Treating Dependent Events in Reliability Evaluations | 2013 | |
| Radiological Risk Curves for the Liquid Radioactive Waste Transfer from Angra 1 to Angra 2 Nuclear Power PLants by a Container Tank | 2013 | |
| On the Applicability of the Critical Safety Function Concept to a Uranium Hexafluoride Conversion Unit | 2013 | |
| Unavailability Study of a Safety System of a Light Water Nuclear Power Plant by Bayesian Networks | 2013 | |
| Digital Control of a Steam Generator Through a Dynamic Simulation Model | 2013 | |
| A Licensing Criterion for Particle Accelerator Licensing in Brazil | 2013 | |
| Applying Safety Archetypes to Identify Nonlinear Influencing Factors on the Fukushima Daiichi Accident | 2013 | |
| Critérios de Classificação Aplicados ao Licenciamento de Aceleradores de Partículas | 2013 | |
| Probabilistic Preferences Composition for Failure Mode Priorization in FMEA | 2013 | |
| DFM/ATHEANA Methodology for Human Failure Analysis of a Simplified Digital Control System for a Nuclear Power Plant Pressurizer | 2013 | |
| Licensing Criteria for Particle Accelerators Categorization | 2013 | |
| Incorporating reliability attributes into the maintenance rule forthe qualified life extension of nuclear power plant safety systems | 2012 | |
| Safety and risk analysis of liquid radioactive waste transfer from Angra 1 to Angra 2 nuclear power plants through a container tank | 2012 | |
| The use of a root cause analysis method for industrial plant reliability improvement and engineering and engineering design feedback | 2012 | |
| A behavior-based monitoring system for safety management | 2012 | |
| Quantifying human error probabilities through a human factors assessment tool | 2012 | |
| A Fokker-Planck model of pitting corrosion in underground pipeline to support a risk-informed decision making | 2011 | |
| A review of different approaches for developing process safety indicators | 2011 | |
| Application of the dynamic HAZOP to an air separation distillation column | 2011 | |
| An approach based on defense in depth and diversity for the reliability assessment of digital instrument and control systems of nuclear power plants | 2011 | |
| Analysis of the effects of explosion of a hydrogen cylinder on the transfer of radioactive liquid wastes at nucler power stations | 2011 | |
| The treatment of commission errors in first generation human reliability analysos methods | 2011 | |
| Analysis of a simplified digital control system for a nuclear power plant pressurizer through the dynamic flowgraph methodology | 2010 | |
| A quality risk analysis considering human factors for bioproceses | 2010 | |
| Does interpreting the human factor as a cooperation quality improve our capability of understanding the nature of industrial hazards? | 2010 | |
| A dynamic failure evaluation of a simplified digital control system of a nuclear power plant pressurizer | 2010 | |
| Uma abordagem da regulamentação com informação do risco da análsie de segurança de sisemas de instrumentação e controle digital aplicados a centrais nucleares | 2010 | |
| Functional reliability study of the electrical power system, automation system and ballast system to maintain the balance of a FPSO platform | 2010 | |
| A Proposal of Safety Indicators Aggregation to Assess the Safety Management Effectiveness of Nuclear Power Plants | 2009 | |
| Multiobjective optimization of test policies for GRP-modeled aging systems | 2009 | |
| Aging Evaluation for the Extension of Qualified Life of Nuclear Power Plant Equipment through Modulated Poisson Processes | 2009 | |
| A Review of the Models for Evaluating Organizational Factors in Human Reliability Analysis | 2009 | |
| A Stochastic Reliability Model for Nuclear Power Plant Safety Systems Considering the Qualified Life Extension and the Maintenance Effectiveness Monitoring Program | 2009 | |
| Potential Exposures and Lessons Learned from Industrial Radiological Accidents | 2008 | |
| Genetic Algorithm Optimization of Preventive Maintenance Scheduling for Repairable Systems Modeled by Generalized Renewal Process | 2008 | |
| An Analysis of the Human Reliability of the Accident in the Plant of TMI Considering THERP and ATHEANA Methodologies | 2008 | |
| A LOPA Application to the Hydrogen Cooling System of the Main Electric Generator of a Nuclear Power Plant | 2008 | |
| Simplificação de Diagramas de Transição em Análises Markovianas de Confiabilidade pela GPT | 2008 | |
| Um Estudo de Confiabilidade para uma Modificação de Projeto do Sistema de Refrigeração de Serviço de Segurança de uma Usina Nuclear do Tipo PWR | 2008 | |
| An Aging Simulation Model for the Emergency Diesel Generators of Angra 2 by Supplementary Variables | 2008 | |
| Quantification of Human Reliability Based on Cognitive Mechanisms of Human Errors | 2007 | |
| An Industry Monitoring System as a Safety Management Tool | 2007 | |
| Estimation of Mean Time to Failure of a Near Surface Radioactive Waste Repository for PWR Power Stations | 2007 | |
| A Reliability Analysis of the Emergency Diesel Generators of a Four Loop PWR under Aging and Perfect Repair by Supplementary Variables | 2007 | |
| An Application of Layers of Protection Analysis (LOPA) to the Evaluation of Fire Hazard Associated to Shutdown Cable Routes of a Nuclear Reactor | 2007 | |
| Reliability Evaluation of the Safety Service Cooling Water System of Angra 2 in the Context of External Events | 2007 | |
| Application of Integrated Optimization to the Control Room Air-Conditioning System of the Angra I Nuclear Power Plant | 2007 | |
| Impact of Failure Data Specialization in Quantitative Risk Assessment of Process Plants | 2006 | |
| Avaliação de Tecnologias de Geração de Energia Utilizando Análise Relacional Grey | 2006 | |
| Análise Numérica para o Sistema Auxiliar de Alimentação de Angra I Usando Variáveis Suplementares de 4 Estados | 2006 | |
| Atualização da Análise de Riscos do Laboratório de Calibração de Monitores de Radiação da Central Nuclear Almirante Álvaro Alberto | 2005 | |
| Modelagem e Avaliação da Extensão da Vida Útil de Plantas Industriais | 2005 | |
| Discussão sobre a Convergência do Método de Euler Iterativo para o Cálculo das Probabilidades de Falha para um Sistema Modelado pelo Método das Variáveis Suplementares | 2005 | |
| Uma Demonstração do Teorema da Existência e Unicidade via Equações Integrais para um Sistema Modelado por Variáveis Suplementares de Dois Estados | 2005 | |
| Aplicação de Algoritmos Genéticos a um Modelo Matemático para o Cálculo da Disponibilidade de Sistemas | 2005 | |
| A New Method for Reliability Evaluation of Auxiliary Feedwater System by the Method of Supplementary Variables | 2005 | |
| Estimação das Probabilidades de Erro Humano de uma APS Nível 1 de uma Usina PWR pela Metodologia do EPRI | 2005 | |
| Aplicação de um Modelo Grey-DEA à Análise Comparativa de Riscos entre Tecnologias de Geração de Energia | 2005 | |
| Uma Aplicação da Teoria de Confiabilidade a Sistemas de Segurança sob Envelhecimento | 2005 | |
| Numerical Evaluation of Angra 1 Auxiliary Feedwater System Reliability by the Method of Supplementary Variables | 2005 | |
| Uma Demonstração do Teorema da Existência e Unicidade via Equações Integrais para um Sistema Modelado por Variáveis Suplementares | 2005 | |
| A Model of Fractional Factorial Design of Experiments in Aircraft Components Engines | 2005 | |
| Opacidade em Sistemas Complexos | 2005 | |
| A Confiabilidade Humana no Controle de Processos Contínuos: Estudo de Caso no Centro de Controle de Gasodutos da Transpetro | 2005 | |
| Especialização de Dados de Falha em Análise Quantitativa de Riscos de Plantas de Processo | 2005 | |
| Aplicação de Algoritmos Genéticos à Otimização Integrada da Disponibilidade de Sistemas de Segurança | 2005 | |
| Utilização de um Modelo de Envelopamento de Dados para Propor Melhorias em Segureança: Uma Abordagem Baseada em FMEA | 2005 | |
| Avaliação da Indisponibilidade de Sistemas Associada a Falhas de Causa Comum Considerando Diversidade e Envelhecimento | 2005 | |
| An Application of Modulated Poisson Processes to the Reliability Analysis of Repairable Systems | 2005 | |
| Probabilidade de Liberação Líquida de Radionuclídeos de um Repositório Próximo à Superfície | 2005 | |
| Confiabilidade de Embalados de Rejeitos Radioativos em Repositórios Próximos à Superfície | 2005 | |
| Um Estudo Utilizando Planejamento de Experimentos para Identificação de Parâmetros Ótimos em Soldagem | 2005 | |
| A Multiobjective Genetic Algorithm for the Optimization of Nuclear Safety Systems Testing and Cost Policies | 2004 | |
| Cálculo Numérico da Disponibilidade do Sistema de Alimentação de Angra 1 pelo Método das Variáveis Suplementares | 2004 | |
| Safety Culture of Nuclear Research and Development Organizations: A Case Study | 2004 | |
| TIg Repair Welding with Pulsed Wire (Dabber-Tig) for Inconnel 718 | 2004 | |
| Comparative Study of Factorial Design Experiments of Optimal Welding Parameters for Commercial Aircraft Components | 2004 | |
| Avaliação Estatística da Gestão da Manutenção e Acompanhamento do Grau de Obsolescência de Máquinas Marítimas Militares | 2003 | |
| O Planejamento de Experimentos Fatorial Aplicado na Determinação de Parâmetros Ótimos de Soldagem | 2003 | |
| Emergency Diesel Generator System Surveillance Test Policy Optimization Through Genetic Algorithms Using Non-periodic Intervention Frequencies and Seasonal Constraints | 2002 | |
| Safety Culture of Complex Risky Systems. The Nuclear Engineering Institute Case Study | 2002 | |
| A Probabilistic Fire Hazard Analysis of Power Cable Routes to Shutdown Equipment | 2002 | |
| Avaliação da Disponibilidade dos Sistemas de Refrigeração de Componentes e Geradores Diesel de Emergência de Angra II Considerando Outage Times | 2002 | |
| Modelo Integrado de Gestão Organizacional de Excelência | 2002 | |
| Modelo de Gestão pela Segurança Total | 2002 | |
| Gestão Organizacional de Excelência: uma Abordagem Orientada para a Segurança | 2002 | |
| A Total Safety Management Model | 2002 | |
| An Integrated Organizational Management Approach to Safety | 2002 | |
| Procedimentos de Cálculo para a Previsão da Vida Residual de Estruturas Oceânicas | 2002 | |
| Unavailability of an Elevating Station by Discrete Event Simulation | 2001 | |
| Otimização de Políticas de Manutenção Preventiva de Sistemas Industriais por Algoritmos Genéticos Usando um Modelo de Disponibilidade e Custos | 2001 | |
| Programa de Mudança Organizacional no Instituto de Engenharia Nuclear - Estágio Atual e Perspectivas | 2001 | |
| Coupled Emergency Diesel Generator-Component Cooling Water System Maintenance Scheduling Optimization by Genetic Algorithms | 2000 | |
| Optimization of the Device of Stages through Genetic Algorithms for Non-Markovian Systems Reliability Evaluation: An Application to Nuclear Safety Systems | 2000 | |
| A New Approach for the Availability Evaluation of Series Components | 2000 | |
| Identification of Repairable Systems Degradation through the Analysis of Periodic Testing Results | 2000 | |
| Analysis of Deterministic and Statistical Approaches to Fatigue Crack Growth in Pressure Vessels | 2000 | |
| Um Modelo Computacional para o Cálculo da Confiabilidade de Geradores de Vapor a partir de Defeitos em seus Tubos | 2000 | |
| Systems Reliability Evaluation under Aging by the Device of Stages Optimized through Genetic Algorithms | 2000 | |
| Cálculo da Indisponibilidade do Sistema de Água de Alimentação Auxiliar de uma Usina PWR Típica por Simulação por Eventos Discretos Orientados a Objetos | 2000 | |
| Reliability Appraisal for a PWR Auxiliary Feedwater System under Aging by Point Processes | 1999 | |
| A Non-Stationary Point Process Maintenance Model for Multi-Unit Systems | 1998 | |
| Reliability Analysis of Service Water Pumps by Poisson Point Processes with a Generalized Model for the Rate of Occurrence of Failures | 1997 | |
| Aplicacao de uma Nova Metodologia Baseada na Propagacao Estatistica de Incertezas para Avaliar os Limites do DNB | 1997 | |
| Weibull Aging Models for the Single Protective Channel Unavailability Analysis by the Device of Stages | 1997 | |
| Manutenção Centrada em Confiabilidade Aplicada ao Sistema de Água de Alimentação Auxiliar de uma Usina Nuclear | 1997 | |
| Análise da Confiabilidade dos Barramentos Elétricos de Segurançade Angra I Considerando a nova Configuração de Geradores Diesel | 1997 | |
| Influence of the Inservice Inspection on the Reliability of a Pressure Vessel under Stress Corrosion Cracking | 1997 | |
| Impact of Surveillance Test Interval Extension on the Core-Melt Frequency: A Methodological Approach | 1997 | |
| Estudo da Importância e Sensibilidade dos Parâmetros Utilizados na Análise da Confiabilidade do Sistema de Água de Alimentação Auxiliar de Angra 1 | 1997 | |
| A Queueing Model for the Reliability Analysis of a System Considering its Age as a Supplementary Variable | 1997 | |
| Análise da Confiabilidade das Bombas de Água de Serviço por uma Abordagem Dinâmica aos Processos Não-Homogêneos de Poisson | 1997 | |
| Análise da Confiabilidade de Simulações de Transporte de Nêutrons para Avaliação de Propriedades Físicas de Materiais Usando o Código MCNP3B | 1997 | |
| Um Modelo de Manutenção Baseado em Processos Pontuais Não-Estacionários para Sistemas com Vários Componentes | 1997 | |
| Aplicação de Processos Pontuais à Análise de Confiabilidade das Bombas de Água de Serviço de uma Usina Nuclear | 1996 | |
| Aplicação do Processo Não-Homogêneo de Poisson à Análise de Confiabilidade de Sistemas Reparáveis de uma Usina Nuclear com Taxas de Ocorrência de Falha Variantes no Tempo | 1996 | |
| Análise Markoviana da Indisponibilidade de um Sistema de Reserva Considerando o seu Teste | 1996 | |
| Confiabilidade de um Canal de Proteção Considerando Envelhecimento pelo Método das Variáveis Suplementares | 1996 | |
| Indisponibilidade do Sistema de Água de Alimentação Auxiliar de Angra 1 Considerando Falhas de Causa Comum pelo Método das Letras Gregas Múltiplas | 1996 | |
| Confiabilidade de Bombas Centrífugas Submersas Considerando Fatores de Prognóstico Relacionados | 1995 | |
| Utilização de Modelos de Regressão em Engenharia de Confiabilidade | 1995 | |
| Accident Rate Evaluation of a Single Protective Channel with Gamma-distributed Downtimes by the Device of Stages | 1995 | |
| An Application of Poisson Point Processes to the Reliability Analysis of Repairable Systems of Nuclear Power Plants | 1995 | |
| Analysis of the Influence of the Demand Rate on the Accident Rate of a Plant Equipped with a Single Protective Channel by GPT Methods | 1995 | |
| Evaluation of the Rupture Probability of a LPG Storage Sphere due to Cracks in Welded Joints | 1995 | |
| A Model for the Reliability Analysis of a Protective Channel Including its Test Period | 1995 | |
| Reliability Analysis of a Protective Channel with Lognormal Downtimes by the Device of Stages | 1995 | |
| Markovian Models for the Reliability Analysis of Multichanneled Protective Systems | 1994 | |
| Utilização do Método dos Estágios na Análise da Indisponibilidade de um Canal de Proteção com Tempos de Reparo Não-exponenciais | 1994 | |
| Utilização de Distribuições de Probabilidade na Análise da Ruptura de Esferas de GLP pela Mecânica da Fratura Probabilística | 1994 | |
| A Markovian Renewal Model for Evaluating the Hazard Rate of a Protective Channel | 1993 | |
| A Markovian Model for the Reliability Analysis of Multichanneled Protective Systems Considering Revealed Failures and Common Cause Failures by the Alpha Model | 1993 | |
| Cost-Effectiveness Analysis of Risk-reduction Measures Related to Extra Redundant Safety Equipment for Angra 1 Nuclear Power Plant | 1993 | |
| Análise da Confiabilidade de uma Esfera de Estocagem de GLP pela Mecânica da Fratura Probabilística Considerando Trincas nas Juntas Soldadas | 1993 | |
| Modernização do Departamento de Engenharia Nuclear da Escola de Engenharia da UFRJ | 1992 | |
| Uma Proposta de Modernização do Departamento de Engenharia Nuclear da UFRJ, Parte 5: A Área de Segurança de Instalações Industriais | 1992 | |
| Análise da Freqüência de Blackout do Sistema Elétrico de uma Instalação Petroquímica por Árvores de Eventos Sujeitas a Condições de Contorno | 1991 | |
| Hazard Rate for a Two-Channel Protective System Subject to a High Demand Rate | 1989 | |
| Aplicação da Análise de Confiabilidade à Manutenção de Equipamentos em Instalações Industriais | 1989 | |
| Análise de Confiabilidade de Sistemas de Proteção | 1989 | |
| Avaliação Quantitativa de Falhas de Causa Comum em Análises de Confiabilidade de Sistemas | 1989 | |
| Aplicação da Análise de Confiabilidade em Instalações Petroquímicas | 1989 | |
| Análise Probabilística da Perda de Potência Elétrica Externa em Angra 1 Considerando Propagação de Incertezas | 1988 | |
| Limits of Expenditure in Risk-Reduction Measures: The Brazilian Case | 1988 | |
| Sobre a Metodologia de Análise de Árvores de Eventos Utilizada no Estudo Probabilístico de Segurança de Angra 1 | 1986 | |
| Computer-Aided Event Tree Analysis with Uncertainty Propagation | 1985 | |
| Some Insights on the Event Tree Methodology Used for the Ongoing Angra 1 PRA | 1985 | |
| Emergency Diesel Generator Configurations: A Value-Impact Analysis for Improving Angra 1 Nuclear Power Plant Availability | 1985 | |
| ETAP-1: A Code for Performing Event-Tree Analyses | 1984 |