Reactor coolant pump monitoring and diagnostic system
Conference
·
OSTI ID:6979081
- Argonne National Lab., IL (USA)
- Maryland Univ., Baltimore, MD (USA)
In order to reliably and safely operate a nuclear power plant, it is necessary to continuously monitor the performance of numerous subsystems to confirm that the plant state is within its prescribed limits. An important function of a properly designed monitoring system is the detection of incipient faults in all subsystems (with the avoidance of false alarms) coupled with an information system that provides the operators with fault diagnosis, prognosis of fault progression and recommended (either automatic or prescriptive) corrective action. In this paper, such a system is described that has been applied to reactor coolant pumps. This system includes a sensitive pattern-recognition technique based upon the sequential probability ratio test (SPRT) that detects incipient faults from validated signals, an expert system embodying knowledge bases on pump and sensor performance, extensive hypertext files containing operating and emergency procedures as well as pump and sensor information and a graphical interface providing the operator with easily perceived information on the location and character of the fault as well as recommended corrective action. This system is in the prototype stage and is currently being validated utilizing data from a liquid-metal cooled fast reactor (EBR-II). 3 refs., 4 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6979081
- Report Number(s):
- CONF-901090-1; ON: DE90011168
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
ARTIFICIAL INTELLIGENCE
BREEDER REACTORS
COOLING SYSTEMS
EBR-2 REACTOR
ENERGY SYSTEMS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PUMPS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MONITORING SYSTEMS
REACTORS
REMOTE SENSING
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
THERMAL POWER PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
ARTIFICIAL INTELLIGENCE
BREEDER REACTORS
COOLING SYSTEMS
EBR-2 REACTOR
ENERGY SYSTEMS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PUMPS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MONITORING SYSTEMS
REACTORS
REMOTE SENSING
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
THERMAL POWER PLANTS