Operator reliability study for Probabilistic Safety Analysis of an operating research reactor

2015 ◽  
Vol 80 ◽  
pp. 409-415 ◽  
Author(s):  
F. Mohamed ◽  
A. Hassan ◽  
R. Yahaya ◽  
I. Rahman ◽  
M. Maskin ◽  
...  
Keyword(s):  
Research Reactor ◽  
Safety Analysis ◽  
Reliability Study ◽  
Probabilistic Safety

scholarly journals Human reliability analysis of the Tehran research reactor using the SPAR-H method

2012 ◽  
Vol 27 (3) ◽  
pp. 319-332 ◽  
Author(s):  
Ramin Barati ◽  
Saeed Setayeshi
Keyword(s):  
Reliability Analysis ◽  
Research Reactor ◽  
Safety Analysis ◽  
Human Action ◽  
Human Reliability ◽  
Human Reliability Analysis ◽  
Human Errors ◽  
Performance Shaping Factors ◽  
Tehran Research Reactor ◽  
Probabilistic Safety

The purpose of this paper is to cover human reliability analysis of the Tehran research reactor using an appropriate method for the representation of human failure probabilities. In the present work, the technique for human error rate prediction and standardized plant analysis risk-human reliability methods have been utilized to quantify different categories of human errors, applied extensively to nuclear power plants. Human reliability analysis is, indeed, an integral and significant part of probabilistic safety analysis studies, without it probabilistic safety analysis would not be a systematic and complete representation of actual plant risks. In addition, possible human errors in research reactors constitute a significant part of the associated risk of such installations and including them in a probabilistic safety analysis for such facilities is a complicated issue. Standardized plant analysis risk-human can be used to address these concerns; it is a well-documented and systematic human reliability analysis system with tables for human performance choices prepared in consultation with experts in the domain. In this method, performance shaping factors are selected via tables, human action dependencies are accounted for, and the method is well designed for the intended use. In this study, in consultations with reactor operators, human errors are identified and adequate performance shaping factors are assigned to produce proper human failure probabilities. Our importance analysis has revealed that human action contained in the possibility of an external object falling on the reactor core are the most significant human errors concerning the Tehran research reactor to be considered in reactor emergency operating procedures and operator training programs aimed at improving reactor safety.

Probabilistic safety analysis of a Greek Research Reactor

2004 ◽  
Vol 31 (5) ◽  
pp. 481-516 ◽  
Author(s):  
O.N Aneziris ◽  
C Housiadas ◽  
M Stakakis ◽  
I.A Papazoglou
Keyword(s):  
Research Reactor ◽  
Safety Analysis ◽  
Probabilistic Safety

OKBM Afrikantov Experience in Developing Methods and Computer Codes for Reliability Analysis and Probabilistic Safety Analysis of Nuclear Installations

Atomic Energy ◽  
2021 ◽  
Author(s):  
L. V. Abramov ◽  
A. V. Baklanov ◽  
A. M. Bakhmet’ev ◽  
I. A. Bylov ◽  
A. A. Vasyuchenkov ◽  
...  
Keyword(s):  
Reliability Analysis ◽  
Safety Analysis ◽  
Computer Codes ◽  
Probabilistic Safety

Seismic probabilistic safety analysis of unit 1 of the Loviisa nuclear power plant

1996 ◽  
Vol 160 (3) ◽  
pp. 411-426
Author(s):  
P. Varpasuo ◽  
J. Puttonen ◽  
M.K. Ravindra
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Analysis ◽  
Probabilistic Safety

Research and Software Implementation of Seismic Probabilistic Safety Analysis Quantification Method

2017 ◽  
Author(s):  
Wei Gao ◽  
Guofeng Tang ◽  
Jingyu Zhang ◽  
Qinfang Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Fragility Curves ◽  
Safety Analysis ◽  
Fukushima Accident ◽  
Binary Decision ◽  
Plant Level ◽  
Accurate Quantification ◽  
Probabilistic Safety

Seismic risk of nuclear power plant has drawn increasing attention after Fukushima accident. An intensive study has been carried out in this paper, including sampling of component and structure fragility based on Monte Carlo method, fragility analysis on system or plant level, convolution of seismic hazard curves and fragility curves. To derive more accurate quantification results, the binary decision diagram (BDD) algorithm was introduced into the quantification process, which effectively reduces the deficiency of the conventional method on coping with large probability events and negated logic. Seismic Probabilistic Safety Analysis (PSA/PRA) quantification software was developed based on algorithms discussed in this paper. Tests and application has been made for this software with a specific nuclear power plant seismic PSA model. The results show that this software is effective on seismic PSA quantification.

Probabilistic safety analysis of maintainable systems

2003 ◽  
Vol 9 (3) ◽  
pp. 303-320 ◽  
Author(s):  
B.S. Dhillon ◽  
Fahri Kirmizi
Keyword(s):  
Safety Analysis ◽  
Probabilistic Safety

scholarly journals Probabilistic Safety Analysis of High Speed and Conventional Lines Using Bayesian Networks

2016 ◽  
Author(s):  
Zacarias Grande Andrade ◽  
Enrique Castillo Ron ◽  
Alan O'Connor ◽  
Maria Nogal
Keyword(s):  
Bayesian Network ◽  
High Speed ◽  
Human Error ◽  
Driver Behavior ◽  
Safety Evaluation ◽  
Safety Analysis ◽  
Human Errors ◽  
Maintenance Costs ◽  
Railway Line ◽  
Probabilistic Safety

A Bayesian network approach is presented for probabilistic safety analysis (PSA) of railway lines. The idea consists of identifying and reproducing all the elements that the train encounters when circulating along a railway line, such as light and speed limit signals, tunnel or viaduct entries or exits, cuttings and embankments, acoustic sounds received in the cabin, curves, switches, etc. In addition, since the human error is very relevant for safety evaluation, the automatic train protection (ATP) systems and the driver behavior and its time evolution are modelled and taken into account to determine the probabilities of human errors. The nodes of the Bayesian network, their links and the associated probability tables are automatically constructed based on the line data that need to be carefully given. The conditional probability tables are reproduced by closed formulas, which facilitate the modelling and the sensitivity analysis. A sorted list of the most dangerous elements in the line is obtained, which permits making decisions about the line safety and programming maintenance operations in order to optimize them and reduce the maintenance costs substantially. The proposed methodology is illustrated by its application to several cases that include real lines such as the Palencia-Santander and the Dublin-Belfast lines.DOI: http://dx.doi.org/10.4995/CIT2016.2016.3428

Sign in / Sign up

Export Citation Format

Share Document