Development and testing of an integrated signal validation system for nuclear power plants. Final Report, Volume 2

Technical Report · Fri Sep 01 00:00:00 EDT 1989

DOI:https://doi.org/10.2172/5229457· OSTI ID:5229457

Upadhayaya, B. R. ^[1]; Kerlin, T. W. ^[1]; Holbert, K. E. ^[1]; Glockler, O. ^[1]; Morgenstern, V. M. ^[1]; Frei, Z. ^[1]; Olvera, J ^[1]

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1. Univ. of Tennessee, Knoxville, TN (United States). Dept. of Nuclear Engineering

The approach for signal validation, instrument fault isolation and characterization incorporates some of the methods used in the past, and new techniques developed under this project. The general architecture consists of parallel signal processing modules. Each of the modules performs a specific task. The current architecture consists of seven signal processing modules. There is no direct communication between the modules. Any cross information desired must be requested at the system executive level. 26 refs., 102 figs., 39 tabs.

• Research Organization: Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering; Combustion Engineering, Inc., Chattanooga, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC02-86NE37959
• OSTI ID: 5229457
• Report Number(s): DOE/NE/37959-35; ON: DE90004013; TRN: 90-002846
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
NUCLEAR POWER PLANTS
INFORMATION VALIDATION
PWR TYPE REACTORS
ALGORITHMS
AUTOMATION
COMPUTER ARCHITECTURE
COMPUTERIZED CONTROL SYSTEMS
DATA ACQUISITION
DATA BASE MANAGEMENT
DATA COVARIANCES
DATA PROCESSING
DECISION MAKING
DESIGN
E CODES
EBR-2 REACTOR
ERRORS
EXPERIMENTAL DATA
FREQUENCY ANALYSIS
MAN-MACHINE SYSTEMS
PERFORMANCE TESTING
PROBABILISTIC ESTIMATION
PROGRESS REPORT
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR SAFETY
RECOMMENDATIONS
REMOTE SENSING
RESEARCH PROGRAMS
SIGNALS
TRANSIENTS
BREEDER REACTORS
COMPUTER CODES
CONTROL SYSTEMS
DATA
DOCUMENT TYPES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
INFORMATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANAGEMENT
MATHEMATICAL LOGIC
NUCLEAR FACILITIES
NUMERICAL DATA
POWER PLANTS
POWER REACTORS
PROCESSING
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
TESTING
THERMAL POWER PLANTS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210500 - Power Reactors
Breeding
220900 - Nuclear Reactor Technology- Reactor Safety
990200 - Mathematics & Computers