Abstract
The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSAS is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category.
Work supported by the U.S. Nuclear Regulatory Commission, Office of Analysis and Evaluation of Operational Data under DOE Contract No. DE-AC07-76IDOl570
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References
F. Hayes-Roth, “The Knowledge-Based Expert System: A Tutorial Computer,” September, 1984.
M. A. Bray, D. E. Sebo, and B. W. Dixon, “Reactor Safety Assessment System - A Situation Assessment System for USNRC Emergency Response”, IEEE Proceedings of the Expert Systems in Government Symposium McLean, Virginia, October 24–25, 1985.
W. J. Clancy, “Heuristic Classification,” STAN-CS-1066 Department of Computer Science, Stanford University, Stanford, CA.
W. R. Nelson, “Response Trees for Nuclear Reactor Operations,” National Technical Information Service, Springfield, VA, NUREG/CR-3631, 1984.
W. E. Underwood and R. E. Swanson, “Causal Reasoning and Explanation of Nuclear Power Plant Operation,” ANS Topical Meeting on Computer Applications for Nuclear Power Plant Operation and Control, September 8–12, Pasco, WA, 1985.
C. H. Meijer, “A Critical Function Expert System for Nuclear Power Plants,” The Enlarged Halden Programme Group Meeting on Fuel Performance Experiments and Analysis and Computerized Man-Machine Communication, Loen, Norway, May 23–28, 1985.
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© 1988 Plenum Press, New York
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Sebo, D.E., Bray, M.A., King, M.A. (1988). Reactor Safety Assessment System. In: Majumdar, M.C., Majumdar, D., Sackett, J.I. (eds) Artificial Intelligence and Other Innovative Computer Applications in the Nuclear Industry. Springer, Boston, MA. https://doi.org/10.1007/978-1-4613-1009-9_28
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DOI: https://doi.org/10.1007/978-1-4613-1009-9_28
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