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Liquid-metal fast breeder reactor core transient modeling for faster than real-time analysis

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5446782
A model was developed for faster than real-time liquid-metal fast breeder reactor core transient analysis for purposes of continuous on-line data validation, plant state verification, and fault identification. The basic feature of this model is the use of a nodal approximation for the coolant, cladding, and fuel temperatures that gives adequately accurate power and temperature predictions with very few axial nodes. In applications of this methodology to fast loss-of-flow and overpower transients, computation times of about one-thirtieth of the real transient time per thermal-hydraulic channel were obtained. The predicted coolant and cladding temperature distributions were practically identical to those resulting from detailed finite difference computations. The predicted fuel temperatures differed by -- 1% or less from those obtained from the same finite difference computations. The analysis of the Transient Reactor Test Facility experiment TS-1C and the Experimental Breeder Reactor II experiment SHRT-17 showed very good agreement between model predictions and measurements.
Research Organization:
Argonne National Lab., Reactor Analysis and Safety Div., 9700 South Cass Avenue, Argonne, IL 60439 (USA)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
5446782
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 77:3; ISSN NUTYB
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
COMPUTERIZED SIMULATION
COOLANTS
EBR-2 REACTOR
EFFICIENCY
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FINITE DIFFERENCE METHOD
FLUID MECHANICS
FUEL-CLADDING INTERACTIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
HYDRAULICS
ITERATIVE METHODS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
NUMERICAL SOLUTION
ON-LINE SYSTEMS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
REAL TIME SYSTEMS
RESEARCH AND TEST REACTORS
SIMULATION
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
TEMPERATURE DEPENDENCE
TEST REACTORS
THERMAL REACTORS
THERMODYNAMICS
TRANSIENT OVERPOWER ACCIDENTS
TRANSIENTS
TREAT REACTOR