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Pedro L.C. Saldanha

Observed names: P Saldanha, P. L. C. Saldanha, P.L. Saldanha, P.L.C. Saldanha, Pedro L. C. Saldanha, Pedro L. Cruz Saldanha, Pedro Luiz da Cruz Saladanha, Pedro Luiz da Cruz Saldanha, Pedro Saldanha
ORCID: 0000-0002-7897-5217
Observed ORCID: 0000-0002-7897-5217
OpenAlex ID: A5022471663
An application of non-homogeneous Poisson point processes to the reliability analysis of service water pumps
2001 · Pedro L.C. Saldanha, Elaine A. de Simone, et al. · Nuclear Engineering and Design · 45
Combined use of composition of probabilistic preferences and entropy weighting for failure mode prioritization
2015 · Pauli Garcia, Vanessa Garcia, et al. · CRC Press eBooks · 13
A DFM/Fuzzy/ATHEANA Human Failure Analysis of a Digital Control System for a Pressurizer
2014 · J. M. O. Pinto, P. F. Frutuoso E Melo, et al. · Nuclear Technology · 11
A DFM/ATHEANA human failure analysis of a digital control system for a pressurizer
2013 · J.M.O. Pinto, P.F. Frutuoso e Melo, et al. · CRC Press eBooks · 11
Analysis of the qualified life extension of nuclear safety systems through modulated Poisson point processes
2012 · Pedro L.C. Saldanha, P.F. Frutuoso e Melo · Progress in Nuclear Energy · 11
Human-Machine Interface (HMI) scenario quantification performed by ATHEANA, A Technique for Human Error Analysis
2015 · J Pinto, P Melo, et al. · CRC Press eBooks · 7
A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks
2019 · Ian B. Gomes, Pedro L. Cruz Saldanha, et al. · Science and Technology of Nuclear Installations · 4
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Models for the Reliability Analysis of Digital Instrumentation and Control Systems for Nuclear Power Plants
2016 · Jonathan M.O. Pinto, Ian B. Gomes, et al. · InTech eBooks · 4
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A Fokker-Planck model of pitting corrosion in underground pipelines to support risk-informed decision making
2011 · E Camacho, P Frutuoso e Melo, et al. · CRC Press eBooks · 4
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima
2023 · D. P. Dionizio, P. L. C. Saldanha, et al. · Nuclear Technology · 3
Aging Evaluation for the Extension of Qualified Life of Nuclear Power Plant Equipment Through Modulated Poisson Processes
2009 · Pedro L. C. Saldanha, P. F. Frutuoso e Melo · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 3
Computational modeling of atmospheric dispersion applied to a small modular reactor
2020 · Rodrigo Carneiro Curzio, Bruno da Silva Moura, et al. · International Journal of Advanced Engineering Research and Science · 2
On probability models for the unavailability analysis of safety systems under aging phenomena
1999 · P.F. Frutuoso e Melo, A.C.M. Alvim, et al. · Progress in Nuclear Energy · 2
A qualitative approach of the regulation for the life extension of brazilian nuclear power plants
2022 · Carla Gomes Tinoco Andrade, Maria de Lourdes Moreira, et al. · Brazilian Journal of Radiation Sciences · 1
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Importance measures for performance shaping factors of human reliability analysis
2022 · Tob R. de Albuquerque, José de Jesús R. Oliva, et al. · Process Safety Progress · 1
Safety Aspects in Dry Storage of Spent Nuclear Fuel in Long Term Operation for Brazilian Nuclear Power Plants
2020 · Claudir José Nodari, Pedro Luiz da Cruz Saladanha, et al. · IEEE Latin America Transactions · 1
Estimating BOP Kill-Line Failure Probability Combining High level and Experts Opinion Informations
2018 · MILTON GEORGE FONSECA KAMPFFE, Fernanda Abizethe de Carvalho Duim, et al. · IEEE Latin America Transactions · 1
A preliminary hazard analysis improving the analytical hierarchy process consistency in decision making process for site selection
2013 · Vivian B. Martins, Anna L. Sousa, et al. · CRC Press eBooks · 1
Aging Evaluation for the Extension of Qualified Life of Nuclear Power Plant Equipment
2011 · Pedro Luiz da Cruz Saldanha, Paulo Fernando F. Frutuoso e Melo · InTech eBooks · 1
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Reliability Analysis of Service Water Pumps by Poisson Point Processes with a Generalized Model for the Rate of Occurrence of Failures
1997 · Pedro L.C. Saldanha, Elaine A. de Simone, et al. · Elsevier eBooks · 1
Predictions of the Maneuvers of Spent Fuel Elements in a Nuclear Power Plant to a Dry Storage Unit Using Artificial Intelligence
2026 · Rafaela da Silva Andrade Freitas, Pedro Luiz da Cruz Saldanha, et al. · Nuclear Technology
Análise dos estudos e procedimentos do gerenciamento do envelhecimento por ação da corrosão sob tensão em unidade de armazenamento a seco de combustíveis irradiados com vistas à extensão de vida / Analysis of studies and procedures of the management of aging due to stress corrosion action in a dry storage unit of irradiated fuels with a view to life extension
2022 · Bruno da Silva Moura, Rodrigo Carneiro Curzio, et al. · Brazilian Journal of Development
Priorities Assessment for Nuclear Failure Mode Combining Expert´s Similarity Aggregation and Simulation of Choquet Integrals in a CPP Framework
2022 · Pauli Adriano de Almada Garcia, Luiz Octávio Gavião, et al. · Editora Poisson eBooks
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Experts' opinion-based Bayesian Inference for the Coverage Factor in BOP Reliability
2020 · Pauli Adriano de Almada Garcia, Fernanda Abizethe de Carvalho Duim, et al. · IEEE Latin America Transactions
Priorities Assessment for Nuclear Failure Mode Combining Experts Similarity Aggregation and Simulation of Choquet Integrals in a CPP Framework
2020 · Pauli Adriano de Almada Garcia, Luiz Octávio Gavião, et al. · Anais do Simpósio Brasileiro de Pesquisa Operacional
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Works count: 30
Citation count: 127
H-index: 6
I10-index: 5
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