Expert system applications in support of system diagnostics and prognostics at EBR-II

Conference · Sun Jan 01 00:00:00 EST 1989

OSTI ID:5428869

Lehto, W K; Gross, K C ^[1]

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1. Argonne National Lab., Idaho Falls, ID (USA)

Expert systems have been developed to aid in the monitoring and diagnostics of the Experimental Breeder Reactor-II (EBR-II) at the Idaho National Engineering Laboratory (INEL) in Idaho Falls, Idaho. Systems have been developed for failed fuel surveillance and diagnostics and reactor coolant pump monitoring and diagnostics. A third project is being done jointly by ANL-W and EG G Idaho to develop a transient analysis system to enhance overall plant diagnostic and prognostic capability. The failed fuel surveillance and diagnosis system monitors, processes, and interprets information from nine key plant sensors. It displays to the reactor operator diagnostic information needed to make proper decisions regarding technical specification conformance during reactor operation with failed fuel. 8 refs., 9 figs., 2 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5428869
• Report Number(s): CONF-890899-2; ON: DE90002171; TRN: 89-030983
• Resource Relation: Conference: Joint Korea-United States seminar on expert systems for electric power systems and industries, Seoul (Republic of Korea), 13-18 Aug 1989
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
EBR-2 REACTOR
EXPERT SYSTEMS
COMPUTER GRAPHICS
COMPUTERIZED SIMULATION
COUPLING
CRAY COMPUTERS
D CODES
DATA BASE MANAGEMENT
DECISION MAKING
FIBER OPTICS
FORECASTING
FUEL ELEMENTS
HISTORICAL ASPECTS
PROBABILISTIC ESTIMATION
PUMPS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR MONITORING SYSTEMS
REACTOR SAFETY
REMOTE SENSING
REPUBLIC OF KOREA
SYSTEMS ANALYSIS
TRANSIENTS
ASIA
BREEDER REACTORS
COMPUTER CODES
COMPUTERS
CONTROL SYSTEMS
COOLING SYSTEMS
DEVELOPING COUNTRIES
ENERGY SYSTEMS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANAGEMENT
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SODIUM COOLED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
210500 - Power Reactors
Breeding
990210 - Supercomputers- (1987-1989)
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)