Sequential probability ratio tests for reactor signal validation and sensor surveillance applications
- Maryland Univ., Baltimore, MD (USA)
- Argonne National Lab., IL (USA)
This paper examines the properties of sequential probability ratio tests (SPRT's) and the application of these tests to nuclear power reactor operation. Recently SPRT's have been applied to delayed-neutron (DN) signal data analysis using actual reactor data from the Experimental Breeder Reactor-II, which is operated by Argonne National Laboratory. The implementation of this research as part of an expert system is described. Mathematical properties of the SPRT are investigated, and theoretical results are validated with tests that use DN-signal data taken from the EBR-II in Idaho. Variations of the basic SPRT and applications to general signal validation are also explored. 16 refs., 3 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 7172256
- Report Number(s):
- CONF-900143-30; ON: DE90007797
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
BREEDER REACTORS
DECISION MAKING
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
EXPERT SYSTEMS
FAILURE MODE ANALYSIS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
FUNCTIONS
GAUSS FUNCTION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MODIFICATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
POWER PLANTS
POWER REACTORS
PROBABILISTIC ESTIMATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR INSTRUMENTATION
REACTOR MONITORING SYSTEMS
REACTOR NOISE
REACTOR OPERATION
REACTOR SAFETY
REACTORS
RECOMMENDATIONS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SAFETY
SIGNALS
SODIUM COOLED REACTORS
STATISTICAL MODELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
THERMAL POWER PLANTS
VALIDATION