Acoustics and voiding dynamics during SLSF simulations of LMFBR undercooling transients
Conference
·
OSTI ID:6494487
The SLSF is the largest U.S. in-reactor test vehicle for steady-state and transient experiments in an environment typical of a LMFBR core. The SLSF experiment program, sponsored by the Department of Energy, contributes to the LMFBR safety assurance program by providing data on key phenomena that occur during postulated reactor accidents. This paper describes completed SLSF experiments, in-core instrumentation used, and methods of data interpretation to determine sodium boiling and voiding dynamics. Boiling inception is shown to be identifiable from several types of in-core instruments. Location of the boiling front and void growth derived from experimental data are compared with analytical predictions. These and other data form the basis to improve understanding of accidents and to validate or guide the development of accident analysis methods.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6494487
- Report Number(s):
- CONF-781202--26
- Country of Publication:
- United States
- Language:
- English
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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
BOILING
BOILING DETECTION
BREEDER REACTORS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
ETR REACTOR
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HYDRODYNAMICS
IN PILE LOOPS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
BOILING DETECTION
BREEDER REACTORS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
ETR REACTOR
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HYDRODYNAMICS
IN PILE LOOPS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS