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Simulation-based expert system for nuclear reactor diagnostics: Final report, September 15, 1985-April 30, 1988

Technical Report ·
OSTI ID:5123009
; ;
An expert system methodology combining model- and rule-based algorithms has been developed for diagnosis of off-normal events in nuclear power plants. A rule-based reasoning system is used in a fuzzy logic structure to analyze plant data heuristically to form a set of hypotheses about a particular transient. Hypothesis testing and fault magnitude estimation are performed with simulation programs to model plant behavior. A new parameter estimation algorithm, called the simulation filter, has been developed for accurate simulation of plant dynamics with low-order physical models of plant components. A critical safety function approach is used to delineate the complexity of a power plant. The simulation-based expert system methodology has been incorporated as the Rx code. Validity of the Rx methodology has been tested through simulation of the Three Mile Island accident. Methods of systematically generating diagnostic rules through pattern recognition and fault tree encoding have been developed and demonstrated on a preliminary basis.
Research Organization:
Michigan Univ., Ann Arbor (USA). Dept. of Nuclear Engineering
DOE Contract Number:
AC02-85NE37945
OSTI ID:
5123009
Report Number(s):
DOE/NE/37945-T1; ON: DE88010182
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CODES
DOCUMENT TYPES
EXPERT SYSTEMS
MATHEMATICAL MODELS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROGRESS REPORT
R CODES
REACTOR PROTECTION SYSTEMS
SIMULATION
THERMAL POWER PLANTS