Search Results - "Frutuoso e Melo, P.F."
-
1
A critical review of methods and models for evaluating organizational factors in Human Reliability Analysis
Published in Progress in nuclear energy (New series) (01-08-2014)“…This work makes a critical evaluation of the deficiencies concerning human factors and evaluates the potential of quantitative techniques that have been…”
Get full text
Journal Article -
2
Including severe accidents in the design basis of nuclear power plants: An organizational factors perspective after the Fukushima accident
Published in Annals of nuclear energy (01-05-2015)“…•The Fukushima accident was man-made and not caused by natural phenomena.•Vulnerabilities were known by regulator and licensee but measures were not…”
Get full text
Journal Article -
3
Stochastic and deterministic models to evaluate the critical distance of a near surface repository for the disposal of intermediate and low level radioactive wastes
Published in Nuclear engineering and design (01-06-2015)“…•The water infiltration scenario is evaluated for a near surface repository.•The main objective is the determination of the critical distance of the…”
Get full text
Journal Article -
4
A method for the identification of a set of critical safety functions for a uranium hexafluoride conversion plant
Published in Annals of nuclear energy (01-05-2016)“…•The purpose is to define a critical safety function set for a conversion plant.•Hazard identification techniques have been considered in the analysis.•The…”
Get full text
Journal Article -
5
Evaluation of the probability of overflow from the Abadia de Goiás repository by the Fokker-Planck equation using the Trotter’s formula
Published in Nuclear engineering and design (01-11-2023)“…•The Fokker-Planck equation is used to obtain the overflow probability of a waste repository.•It is a radioactive near surface repository for the Goiania…”
Get full text
Journal Article -
6
A mass and energy balance for a specific refuelling of Angra 2 nuclear power plant from a life cycle perspective
Published in Nuclear engineering and design (01-07-2024)“…•A mass and energy balance for a cycle of Angra 2 plant is performed with real data.•A life cycle analysis approach was used in order to allow for…”
Get full text
Journal Article -
7
A review of the cognitive basis for human reliability analysis
Published in Progress in nuclear energy (New series) (01-11-2019)“…In the early 1990s, criticism over first-generation human reliability analysis (HRA) models, like THERP, SPAR-H, and ASEP, claimed that these models did not…”
Get full text
Journal Article -
8
Preventive Maintenance Policy Optimization of a Nuclear Reactor High Pressure Injection System Using a Reliability-Cost Model
Published in Revista IEEE América Latina (01-04-2005)“…Previous works have demonstrated that Genetic Algorithms (GA) and Probabilistic Safety Analysis (PSA) can be applied to maintenance policy optimization…”
Get full text
Journal Article -
9
Component unavailability model for PSA Level I applications considering aging and startup degradation: An Application to an Emergency Diesel Generator System
Published in Annals of nuclear energy (01-04-2021)“…The paper proposes an unavailability model, which considers standby component degradation due to repeated startups, including not only planned surveillance…”
Get full text
Journal Article -
10
3D simulation model of water infiltration for radioactive waste on a virtual reality Environment: An application to the Abadia de Goiás repository
Published in Annals of nuclear energy (01-06-2020)“…•Virtual environment scenario for a radioactive waste infiltration model.•The aim is to implement a 3D simulation model to a repository safety…”
Get full text
Journal Article -
11
Sensitivity analysis of the accident rate of a plant equipped with a protection channel under aging by the generalized perturbation theory
Published in Annals of nuclear energy (01-10-2022)Get full text
Journal Article -
12
The phased application of STAMP, FRAM and RAG as a strategy to improve complex sociotechnical system safety
Published in Progress in nuclear energy (New series) (01-01-2021)“…Systemic approaches and methods have been developed to adequately deal with the challenge of managing complex sociotechnical system safety (Yousefi et al.,…”
Get full text
Journal Article -
13
Availability assessment of a nuclear reactor limitation system by a Timed Petri Net
Published in Progress in nuclear energy (New series) (01-10-2022)“…The constant evolution of instrumentation and control systems (I & C) of nuclear power plants requires a robust reliability assessment, due to the constant…”
Get full text
Journal Article -
14
Human reliability analysis of the Tokai-Mura accident through a THERP–CREAM and expert opinion auditing approach
Published in Safety science (01-08-2016)“…•Influence of organizational features on human error probability is evaluated.•Expert opinion elicitation and auditing process are used to fill data gaps.•The…”
Get full text
Journal Article -
15
An Itô model of pit corrosion in pipelines for evaluating risk-informed decision making
Published in Nuclear engineering and design (01-11-2015)“…•The aim of this paper is to determine the time evolution of pit corrosion.•The stochastic nature of the corrosion process is governed by an Itô equation.•The…”
Get full text
Journal Article -
16
A fuzzy data envelopment analysis approach for FMEA
Published in Progress in nuclear energy (New series) (2005)“…We present a data envelopment analysis approach for determining ranking indices among failure modes in which the typical FMEA parameters are modeled as fuzzy…”
Get full text
Journal Article Conference Proceeding -
17
Simplification of transition state diagrams via Generalized Perturbation Theory in the Markovian reliability analysis of aging safety systems
Published in Annals of nuclear energy (01-08-2016)“…•Large state transition diagrams in Markovian reliability analysis are a pitfall.•The Generalized Perturbation Theory can help simplify state transition…”
Get full text
Journal Article -
18
Analysis of the qualified life extension of nuclear safety systems through modulated Poisson point processes
Published in Progress in nuclear energy (New series) (01-09-2012)“…The Modulated Power Law Process (MPLP) is a three-parameter stochastic point process that can be used to describe the failure times of repairable systems…”
Get full text
Journal Article -
19
A Root Cause Analysis Method for Industrial Plant Reliability Improvement and Engineering Design Feedback
Published in Chemical engineering transactions (01-01-2013)“…Root cause analysis (RCA) methodologies have been used worldwide to help preventing incidental events from recurring, contributing to avoid losses and worker…”
Get full text
Journal Article -
20
Safety Integrity Level (SIL) Integrated with Human and Organizational Factors
Published in Chemical engineering transactions (01-01-2013)“…From many accident/incidents analysis, human and organizational factors have been identified as root causes or contributing factors. Therefore, in order to…”
Get full text
Journal Article