Model for LMFBR core transient analysis in real time
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6884855
Plant safety as well as plant availability can be significantly improved if functions such as data validation, plant state verification, and fault identification are automated. A methodology for automation of these functions was presented in an earlier paper. To implement this methodology, plant models that run significantly faster than real transient time are needed. Such models for the intermediate heat exchanger and a once-through liquid-metal fast breeder reactor (LMFBR) steam generator have been presented. This paper discusses the modeling of LMFBR core transients. It is shown that, with a proper choice of shape functions, a nodal approximation of the coolant, cladding, and fuel temperature distributions leads to adequately accurate power and temperature predictions, as well as adequately short computation times. From the point of view of operational safety, it is desirable to terminate a transient before sodium boiling is initiated in the core. Thus, only the modeling of the preboiling phase of core transients is discussed.
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 6884855
- Report Number(s):
- CONF-860610-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
- Country of Publication:
- United States
- Language:
- English
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Model for LMFBR core transient analysis in real-time
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Conference
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Tue Dec 31 23:00:00 EST 1985
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OSTI ID:5947849
Liquid-metal fast breeder reactor core transient modeling for faster than real-time analysis
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Mon Jun 01 00:00:00 EDT 1987
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Validation of a model for faster-than-real-time LMFBR core transient analysis
Conference
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Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5528192
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
ACCURACY
AVAILABILITY
BOILERS
BREEDER REACTORS
DISCRETE ORDINATE METHOD
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FINITE DIFFERENCE METHOD
FLUID FLOW
FUEL CANS
HEAT TRANSFER
ITERATIVE METHODS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATHEMATICAL MODELS
NUMERICAL SOLUTION
POWER-COOLING-MISMATCH ACCIDENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
STEAM GENERATORS
TEMPERATURE DISTRIBUTION
TRANSIENTS
VAPOR GENERATORS
210500* -- Power Reactors
Breeding
ACCIDENTS
ACCURACY
AVAILABILITY
BOILERS
BREEDER REACTORS
DISCRETE ORDINATE METHOD
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FINITE DIFFERENCE METHOD
FLUID FLOW
FUEL CANS
HEAT TRANSFER
ITERATIVE METHODS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATHEMATICAL MODELS
NUMERICAL SOLUTION
POWER-COOLING-MISMATCH ACCIDENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
STEAM GENERATORS
TEMPERATURE DISTRIBUTION
TRANSIENTS
VAPOR GENERATORS