Characterizing W-2 SLSF experiment temperature oscillations using computer graphics. [Sodium Loop Safety Facility]
Conference
·
OSTI ID:5348839
The W-2 SLSF (Sodium Loop Safety Facility) experiment was an instrumented in-reactor test performed to characterize the failure response of full-length, preconditioned LMFBR prototypic fuel pins to slow transient overpower (TOP) conditions. Although the test results were expected to confirm analytical predictions of upper level failure and fuel expulsion, an axial midplane failure was experienced. Extensive post-test analyses were conducted to understand all of the unexpected behavior in the experiment. (1) The initial post-test effort focused on the temperature oscillations recorded by the 54 thermocouples used in the experiment. In order to synthesize the extensive data records and identify patterns of behavior in the data records, a computer-generated film was used to present the temperature data recorded during the experiment.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 5348839
- Report Number(s):
- HEDL-SA-2968-S; CONF-831047-131; ON: DE84006346
- Country of Publication:
- United States
- Language:
- English
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Characterizing W-2 SLSF experiment temperature oscillations using computer graphics
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
DATA ANALYSIS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
ETR REACTOR
FAST REACTORS
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IRRADIATION REACTORS
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LIQUID METAL COOLED REACTORS
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OSCILLATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
TANK TYPE REACTORS
TEMPERATURE DISTRIBUTION
TEST REACTORS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
DATA ANALYSIS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
ETR REACTOR
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL PINS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
OSCILLATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
TANK TYPE REACTORS
TEMPERATURE DISTRIBUTION
TEST REACTORS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS