Characterizing W-2 SLSF experiment temperature oscillations using computer graphics. [Sodium Loop Safety Facility]
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
- Resource Relation:
- Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Post-test analysis of the W-2 SLSF experiment. [LMFBR]
Post-test examination observations for the W-2 SLSF experiment. [Sodium Loop Safety Facility]
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
TRANSIENT OVERPOWER ACCIDENTS
REACTOR SAFETY EXPERIMENTS
OSCILLATIONS
DATA ANALYSIS
ETR REACTOR
FUEL PINS
SIMULATION
TEMPERATURE DISTRIBUTION
ACCIDENTS
BREEDER REACTORS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LIQUID METAL COOLED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors