Use of Kalman filter methods in analysis of in-pile LMFBR accident simulations
Conference
·
OSTI ID:5583718
Kalman filter methodology has been applied to inpile liquid-metal fast breeder reactor simulation experiments to obtain estimates of the fuel-clad thermal gap conductance. A transient lumped parameter model of the experiment is developed. An optimal estimate of the state vector chosen to characterize the experiment is obtained through the use of the Kalman filter. From this estimate, the fuel-clad thermal gap conductance is calculated as a function of time into the test and axial position along the length of the fuel pin.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5583718
- Report Number(s):
- CONF-831235-2; ON: DE84000587
- Country of Publication:
- United States
- Language:
- English
Similar Records
Use of Kalman filter methods in analysis of in-pile LMFBR accident simulations
Determination of fuel-clad thermal gap conductance by use of Kalman filter methods
Kalman filter-based gap conductance modeling. [PWR; BWR]
Journal Article
·
Wed Nov 30 23:00:00 EST 1983
· Proceedings of the 22nd IEEE Conference on Decision and Control; (United States)
·
OSTI ID:6258043
Determination of fuel-clad thermal gap conductance by use of Kalman filter methods
Journal Article
·
Sun Aug 01 00:00:00 EDT 1982
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:5870583
Kalman filter-based gap conductance modeling. [PWR; BWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6104958
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES