Evaluation of risk impact of completion time changes combining PSA and DSA model insight and human reliability analysis

Abstract

Highlights  Evaluation risk impact of completion time changes  Combination of deterministic and probabilistic model  Identification of unknown accident sequences using thermo-hydraulic simulations  Increasing human error probability accuracy through best estimate codes  More realistic PSA model

A review of components of reliability for the evaluation of Programmable logic controller

“…Cheng et al (2018) [128] examined the combined issue of condition-based maintenance, quality control, and production lot size for an imperfect production system that is vulnerable to degradation in both reliability and quality. Using a probabilistic safety assessment model that has been improved by a best-estimate safety analysis and a human reliability analysis, Martorell et al (2018) [129] suggested a three-step process to assess the risk impact of modifications to completion time within nuclear power plant technical specifications. The Vehicle Routing Problem (VRP) was examined by Jbili et al (2018) [130] in the context of unique transcontinental transportation scenarios in which large vehicles travel great distances between cities in challenging environments, increasing the likelihood that essential components may fail.…”

A Correlation Analysis Model of Human Factors in Mine Accidents Based on Apriori Algorithm

“…Human reliability refers to the probability that operators complete a task within the specified time in any stage of system operation [4]. As an emerging subject, the evaluation of human reliability aims to quantify and qualify the reliability of operators, making it possible to analyze, predict and reduce human error [5]. As stated by Kirwan [6], human reliability evaluation mainly derives the probability of accidents induced by human error, and finds the way to minimize human error.…”

Aportaciones al modelado de la indisponibilidad de componentes y la fiabilidad humana para la mejora de la seguridad de las centrales nucleares informada en el riesgo

“…La utilización de códigos BE permite descubrir nuevas secuencias accidentales no contempladas en el APS original y una cuantificación más realista de las PEH para las acciones involucradas en las mismas. El caso de aplicación presentado evalúa los cambios en la cuantificación de las PEH y el riesgo del cambio en el CT. Este capítulo amplía la investigación presentada en el artículo de P. Martorell et al (2018).…”