Summary and evaluation of transient test data on extended fuel motion resulting from unprotected loss of flow
Experimental data on fuel failure and its consequences are used to provide predictions of the extended fuel motion that would occur after a hypothetical core-disruptive loss-of-flow accident without scram in the Fast Test Reactor. These data indicate the existence of fuel-dispersal mechanisms, slow collapse of fresh fuel, resistance to collapse of irradiated fuel, the absence of accelerated collapse mechanisms (such as cladding-coolant vapor ''explosions''), and the fact that real LMFBR conditions inhibit rapid sodium-vaporization events. These data indicate that severely damaged subassemblies will not be coolable in situ by returning sodium after the accident, because of steel and fuel blockages, and suggest that the severely damaged, melted fuel will eventually disperse upward under the influence of vapor generated by decay heating.
- Research Organization:
- Argonne National Lab., Ill. (USA)
- Sponsoring Organization:
- US Energy Research and Development Administration (ERDA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 7288836
- Report Number(s):
- ANL-77-40
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
DATA
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
INFORMATION
LIQUID METAL COOLED REACTORS
LOSS OF FLOW
MELTDOWN
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TRANSIENTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
DATA
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
INFORMATION
LIQUID METAL COOLED REACTORS
LOSS OF FLOW
MELTDOWN
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TRANSIENTS