Post-test examination observations for the W-2 SLSF experiment. [Sodium Loop Safety Facility]
Conference
·
OSTI ID:5348860
Gamma scanning measurements revealed that the axial power profile in these test trains was more peaked than expected based on pretest calculations and critical facility measurements. These results implied that the thermal flux incident on the test assembly was greater than expected, which was manifested in highly skewed and extensive fuel melting zones in the outer pin fuel pellets. Observations indicated that the extent of fuel melting near the midplane exceeded 90% of the pellet radius in some of the outer fuel pins toward the end of the overpower transient, with penetration of molten fuel to the cladding inner surface. It is postulated that this extensive fuel melting and penetration combined with bowing-induced high temperature oscillations to produce the initial disruptive failure in an outer pin at the midplane. Subsequent failure events were induced by the inrush of argon fill gas following rupture of the fluted duct tube. Up to one-third of the total fuel inventory was expelled from the test pin bundle into the coolant channels, with substantial upward sweepout of the ejected fuel noted in the post-test examination. The overall nature of the failure event was judged to be relatively nonviolent, based largely on the survival of unclad, free standing fuel pellet columns in the upper levels of the test section. The observed midplane failure in the W-2 experiment has been attributed to conditions unique to the test. These conditions would not exist in full-size LMFBR fuel assemblies, for which fuel pin failure under slow, unprotected TOP conditions would be expected by a different mode at a higher elevation.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 5348860
- Report Number(s):
- HEDL-SA-2962-FP; CONF-831047-132; ON: DE84006345
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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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
CORIUM
ELECTROMAGNETIC RADIATION
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
ETR REACTOR
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
GAMMA RADIATION
INDUSTRIAL RADIOGRAPHY
IONIZING RADIATIONS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MELTING
NEUTRON RADIOGRAPHY
PHASE TRANSFORMATIONS
POST-IRRADIATION EXAMINATION
RADIATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
TANK TYPE REACTORS
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TRANSIENT OVERPOWER ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500 -- Power Reactors
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220600 -- Nuclear Reactor Technology-- Research
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ACCIDENTS
BREEDER REACTORS
CORIUM
ELECTROMAGNETIC RADIATION
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
ETR REACTOR
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
GAMMA RADIATION
INDUSTRIAL RADIOGRAPHY
IONIZING RADIATIONS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MELTING
NEUTRON RADIOGRAPHY
PHASE TRANSFORMATIONS
POST-IRRADIATION EXAMINATION
RADIATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS