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A Quantitative Assessment of Organizational Factors Affecting Safety Using System Dynamics Model  

Yu Jaekook (Korea Electric Power Research Institute)
Ahn Namsung (Korea Electric Power Research Institute)
Jae Moosung (Hanyang University)
Publication Information
Nuclear Engineering and Technology / v.36, no.1, 2004 , pp. 64-72 More about this Journal
Abstract
The purpose of this study is to develop a system dynamics model for the assessment of the organizational and human factors in a nuclear power plant which contribute to nuclear safety. Previous studies can be classified into two major approaches. One is the engineering approach using tools such as ergonomics and Probability Safety Assessment (PSA). The other is the socio-psychology approach. Both have contributed to find organizational and human factors and to present guidelines to lessen human error in plants. However, since these approaches assume that the relationship among factors is independent they do not explain the interactions among the factors or variables in Nuclear Power Plants. To overcome these restrictions, a system dynamics model, which can show cause and effect relationships among factors and quantify the organizational and human factors, has been developed. Handling variables such as the degree of leadership, the number of employees, and workload in each department, users can simulate various situations in nuclear power plant organization. Through simulation, users can get insights to improve safety in plants and to find managerial tools in both organizational and human factors.
Keywords
system dynamics; organijational factors; probabilistic safety assessment;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
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1 R. B. Worrell and D. W. Stack, 1977, Common-cause Analysis Using SETS, SAND77-1832, Sandia National Laboratories, Albuquerque, N. M.
2 R. B. Worrell and D. W. Stack, 1980, 'A Boolean Approach to Common Cause Analysis,' Proceedings, Annual Reliability and Maintainability Symposium, San Francisco, CA, PP. 363-366
3 K. Kang and M. Jae, 2003, 'A Quantitative Assessment on LCO Using A Concept of System Dynamics', Proceedings of ICAPP' 03, Cordoba, Spain, pp.3242-3251
4 PRA PROCEDURES GUIDE, Final Report, Vol.1,2 NUREG/CR-2300, U. S. Nuclear Regulatory Commission, (1982)
5 J. Holmberg, K. Hukki, L. Norros, U. Pukkinen, and P. Pyy, 'An Integrated approach to human reliability analysis-decision analytic dynamic reliability model,' Reliability Engineering & System Safety, Volume 65 (3), 239-250, (1999)   DOI   ScienceOn
6 J. W. Forrester, 'Industrial Dynamics,' The MIT Press, Cambridge, MA, (1981)
7 Philadelphia Electric Company, Probabilistic Risk Assessment, Limerick Generating Station, Docket Nos. 50-352, 50-353, U. S. Nuclear Regulatory Commission, Washington, Washington, D. C., (1981)
8 D. P. Wagner, C. L. Cate, and J. B. Fussell, 1981, The Fault Tree as a Tool in a Safety Analysis in Nuclear Power Plants, INFO-0036, Atomic Energy Control Board, Ottawa