Water tests for determining post voiding behavior in the LMFBR
The most serious of the postulated accidents considered in the design of the Liquid Metal Cooled Fast Breeder Reactor (LMFBR) is the Loss of Pipe Integrity (LOPI) accident. Analysis models used to calculate the consequences of this accident assume that once boiling is initiated film dryout occurs in the hot assembly as a result of rapid vapor bubble growth and consequent flow stoppage or reversal. However, this assumption has not been put to any real test. Once boiling is initiated in the hot assembly during an LMFBR LOPI accident, a substantial gravity pressure difference would exist between this assembly and other colder assemblies in the core. This condition would give rise to natural circulation flow boiling accompanied by pressure and flow oscillations. It is possible that such oscillations could prevent or delay dryout and provide substantial post-voiding heat removal. The tests described were conceived with the objective of obtaining basic information and data relating to this possibility.
- Research Organization:
- Massachusetts Inst. of Tech., Cambridge (USA). Energy Lab.
- OSTI ID:
- 7149440
- Report Number(s):
- ORNL-SUB-4450-1; MIT-EL-76-005
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
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BREEDER REACTORS
DRYOUT
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
BREEDER REACTORS
DRYOUT
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
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LIQUID METAL COOLED REACTORS
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LOSS OF FLOW
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OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
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SIMULATION
STRUCTURAL MODELS
VOIDS
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