Kalman filter-based gap conductance modeling
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5672479
None
- Research Organization:
- EG and G Idaho Inc., P.O. Box 1625, Idaho Falls, ID 83415
- OSTI ID:
- 5672479
- Report Number(s):
- CONF-830609-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 44
- Country of Publication:
- United States
- Language:
- English
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Conference
·
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· Trans. Am. Nucl. Soc.; (United States)
·
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALGORITHMS
ATWS
CHEMICAL ANALYSIS
CONTROL SYSTEMS
DATA COVARIANCES
DELAYED NEUTRON ANALYSIS
FUEL ELEMENTS
FUEL PINS
FUEL-CLADDING INTERACTIONS
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL LOGIC
MATHEMATICAL MODELS
MATHEMATICS
NONDESTRUCTIVE ANALYSIS
NONLINEAR PROBLEMS
NUCLEAR MODELS
NUCLEAR REACTION ANALYSIS
PHYSICAL PROPERTIES
PROBABILISTIC ESTIMATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTORS
REGRESSION ANALYSIS
RESEARCH AND TEST REACTORS
STATISTICS
TANK TYPE REACTORS
TEMPERATURE MEASUREMENT
TEST REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
TRANSIENT OVERPOWER ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALGORITHMS
ATWS
CHEMICAL ANALYSIS
CONTROL SYSTEMS
DATA COVARIANCES
DELAYED NEUTRON ANALYSIS
FUEL ELEMENTS
FUEL PINS
FUEL-CLADDING INTERACTIONS
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL LOGIC
MATHEMATICAL MODELS
MATHEMATICS
NONDESTRUCTIVE ANALYSIS
NONLINEAR PROBLEMS
NUCLEAR MODELS
NUCLEAR REACTION ANALYSIS
PHYSICAL PROPERTIES
PROBABILISTIC ESTIMATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTORS
REGRESSION ANALYSIS
RESEARCH AND TEST REACTORS
STATISTICS
TANK TYPE REACTORS
TEMPERATURE MEASUREMENT
TEST REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
TRANSIENT OVERPOWER ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS