Application of the Saint Code in Modelling and Analyzing Some Human Tasks in Nuclear Power Plants

1981 ◽  
Vol 25 (1) ◽  
pp. 105-109
Author(s):  
A. Mohsen M. Metwally ◽  
Zeinab A. Sabri ◽  
S. Keith Adams ◽  
Abdo A. Husseiny
Keyword(s):  
Task Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Human Error ◽  
Nuclear Power Plants ◽  
Human Performance ◽  
Human Engineering ◽  
Performance Shaping Factors ◽  
Power Plant Operation ◽  
Error Probabilities

Two techniques useful for the simulation and analysis of human performance in tasks involving nuclear power plant operation, maintenance and testing are evaluated. The SAINT and THERP techniques are compared with respect to their relevance to conducting task analysis, estimation of human error probabilities and accounting for performance shaping factors in nuclear power plants. The results show that the SAINT is more flexible and has promising features for human engineering studies of complex systems when compared to the static THERP technique currently used in nuclear safety analysis.

A Data Bank for Human Related Events in Nuclear Power Plants

1982 ◽  
Vol 26 (9) ◽  
pp. 794-798 ◽  
Author(s):  
A. Mohsen M. Metwally ◽  
Zeinab A. Sabri ◽  
S. Keith Adams ◽  
Abdo A. Husseiny
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Human Performance ◽  
Data Bank ◽  
Data Sources ◽  
Human Reliability Analysis ◽  
Performance Shaping Factors ◽  
Comprehensive Survey ◽  
Survey And Evaluation

The authors introduce a comprehensive survey and evaluation of presently available data sources in nuclear power plants. A newly developed classification format for human related events is proposed. The format presents all necessary information in a coded form to support human reliability analysis and the assessment of performance shaping factors. Recommendations are given for improving data sources to facilitate the evaluation of man-machine interfaces and human performance in nuclear power plants.

Use of Influence Diagrams and Fuzzy Theory to Develop Assessment Method of Organizational Influences on Component Maintenance

2002 ◽  
Author(s):  
Yoonik Kim ◽  
Kwang-Won Ahn ◽  
Chang-Hyun Chung ◽  
Kil Yoo Kim ◽  
Joon-Eon Yang
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Human Error ◽  
Nuclear Power Plants ◽  
Fuzzy Theory ◽  
Organizational Factors ◽  
Assessment Method ◽  
Influence Diagrams ◽  
Safety Attitudes ◽  
Organizational Influences

Organization can make influences on all the systems. Especially in case of nuclear power plants in which safety is established to be one of the most important operating goals, there have been a lot of research efforts for the hardware advancement. However in recent years, it has been widely recognized that organizational factors in nuclear power plants have an important influence on the safety attitudes and the safe behavior of individuals. Until now, any means to include assessments of organizational structure in probabilistic risk assessments have not been universally accepted. The objective of this work is to develop a method to assess organizational influences on component maintenance. Influence diagrams are introduced in this method as a decision making tool and fuzzy theory is used to reflect the vagueness in considering relevance of human activities in maintenance tasks. Introducing fuzzy theory to assess the organizational factors is deemed to a somewhat new trial, which makes it possible to convert linguistic vague descriptions into mathematical ones. Fuzzy linguistic descriptions offer an alternative and often complementary language to conventional, i.e., analytic approaches to modeling systems. Among the existing methodologies to assess organizational factors, the concept of the ω-factor model is utilized and the mechanism that organizational factors have influences on component maintenance is evaluated through composing influence diagrams. These influences go to failure rates and eventually affect component unavailability. Further study will make it possible that the influences of organizational factors on human error probabilities are incorporated into human reliability analysis and furthermore probabilistic safety assessment.

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