UNCERTAINTY OF HUMAN ERROR AND FUZZY APPROACH TO HUMAN RELIABILITY ANALYSIS

2006 ◽  
Vol 14 (01) ◽  
pp. 111-129 ◽  
Author(s):  
B. J. KIM ◽  
RAM R. BISHU
Keyword(s):  
Reliability Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Human Error ◽  
Critical Factor ◽  
Fuzzy Approach ◽  
Human Reliability ◽  
Human Reliability Analysis ◽  
Human Errors ◽  
Fuzzy Logic Approach

Human error is regarded as a critical factor in catastrophic accidents such as disasters at nuclear power plants, air plane crashes, or derailed trains. Several taxonomies for human errors and methodologies for human reliability analysis (HRA) have been proposed in the literature. Generally, human errors have been modeled on the basis of probabilistic concepts with or without the consideration of cognitive aspects of human behaviors. Modeling of human errors through probabilistic approaches has shown a limitation on quantification of qualitative aspects of human errors and complexity of attributes from circumstances involved. The purpose of this paper is to investigate the methodologies for human reliability analysis and introduce a fuzzy logic approach to the evaluation of human interacting system's reliability. Fuzzy approach could be used to estimate human error effects under ambiguous interacting environments and assist in the design of error free work environments.

scholarly journals Proof of Concept for a Human Reliability Analysis Method for Heuristic Usability Evaluation of Software

2005 ◽  
Vol 49 (5) ◽  
pp. 676-680 ◽  
Author(s):  
Ronald L. Boring ◽  
David I. Gertman ◽  
Jeffrey C. Joe ◽  
Julie L. Marble
Keyword(s):  
Reliability Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Cost Effective ◽  
Usability Evaluation ◽  
Analysis Method ◽  
Human Reliability ◽  
Human Reliability Analysis ◽  
New Techniques ◽  
Innovative Methods

An ongoing issue within human-computer interaction (HCI) is the need for simplified or “discount” methods. The current economic slowdown has necessitated innovative methods that are results driven and cost effective. The myriad methods of design and usability are currently being cost-justified, and new techniques are actively being explored that meet current budgets and needs. Recent efforts in human reliability analysis (HRA) are highlighted by the ten-year development of the Standardized Plant Analysis Risk HRA (SPAR-H) method. The SPAR-H method has been used primarily for determining humancentered risk at nuclear power plants. The SPAR-H method, however, shares task analysis underpinnings with HCI. Despite this methodological overlap, there is currently no HRA approach deployed in heuristic usability evaluation. This paper presents an extension of the existing SPAR-H method to be used as part of heuristic usability evaluation in HCI.

Methodology and Application of Human Reliability Analysis in CAP1400 Nuclear Power Plant

2017 ◽  
Author(s):  
Yongping Qiu ◽  
Jiandong He ◽  
Juntao Hu ◽  
Yucheng Zhuo ◽  
Jie He
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Reliability Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Human Factor ◽  
Human Reliability ◽  
Human Reliability Analysis ◽  
Human Factor Engineering ◽  
Human Failure

It is well recognized that humans play an important role in the safety operation of nuclear power plants (NPPs). Usually three types of human interactions (HIs) are defined in the human reliability analysis (HRA) of probabilistic safety assessment (PSA) for NPPs, i.e., pre-initiating event HIs, initiating event-related HIs, and post-initiating event HIs. In this paper, a brief introduction of the HRA methodology for CAP1400 nuclear power plant is first presented, including internal events and external events (mainly internal fire and flooding) HRA. Next, the CAP1400 human failure event quantification content is given with a typical example, and some insights and proposals based on CAP1400 PSA/HRA results are discussed. Finally, the application of HRA in human factor engineering design of CAP1400 is described. The human actions (HAs) most important to safety are identified via a combination of probabilistic and deterministic analyses, and then addressed when conducting the human factor engineering program. The CAP1400 HRA is one of the most important PSA elements and provides fundamental support for CAP1400 PSA and the relevant applications.

Development of a Behaviorally Based Human Reliability Analysis Method

1995 ◽  
Vol 39 (15) ◽  
pp. 1006-1010 ◽  
Author(s):  
Harold S. Blackman ◽  
James C. Byers
Keyword(s):  
Reliability Analysis ◽  
Human Behavior ◽  
Nuclear Power ◽  
Power Plants ◽  
Human Performance ◽  
Nuclear Regulatory Commission ◽  
Analysis Method ◽  
Human Reliability ◽  
Information Processing Model ◽  
Human Reliability Analysis

Human reliability analysis (HRA) assesses the safety and risk significance of human tasks. This paper describes the development and testing of a behaviorally based human reliability analysis method. A general criticism of HRA methods is the inability to tie HRA methods back to first principles in human behavior. The method described here, developed for the accident sequence precursor (ASP) program of the U. S. Nuclear Regulatory Commission (NRC), begins by first describing an information processing model of human behavior, and then using it to define a comprehensive list of factors that influence human performance. These psychological factors are then distilled into the practical and operational factors more commonly identified in nuclear power plant operation. Appropriate adjustments for level of detail are then made to the factors and a further model developed to evaluate the effect of dependency between human actions. The application of the method to the ASP models for two nuclear power plants is discussed.

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