Development of a model to predict flow oscillations in low-flow sodium boiling. [Loss-of-Piping Integrity accidents]
Tests performed in a small scale water loop showed that voiding oscillations, similar to those observed in sodium, were present in water, as well. An analytical model, appropriate for either sodium or water, was developed and used to describe the water flow behavior. The experimental results indicate that water can be successfully employed as a sodium simulant, and further, that the condensation heat transfer coefficient varies significantly during the growth and collapse of vapor slugs during oscillations. It is this variation, combined with the temperature profile of the unheated zone above the heat source, which determines the oscillatory behavior of the system. The analytical program has produced a model which qualitatively does a good job in predicting the flow behavior in the wake experiment. The amplitude discrepancies are attributable to experimental uncertainties and model inadequacies. Several parameters (heat transfer coefficient, unheated zone temperature profile, mixing between hot and cold fluids during oscillations) are set by the user. Criteria for the comparison of water and sodium experiments have been developed.
- Research Organization:
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
- DOE Contract Number:
- AS02-78ET37218
- OSTI ID:
- 6850745
- Report Number(s):
- DOE/ET/37218-2; MIT-EL-80-006; TRN: 81-006668
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
LOSS OF FLOW
SODIUM
BOILING
FLUID FLOW
HEAT TRANSFER
MATHEMATICAL MODELS
OSCILLATIONS
SIMULATION
WATER
ACCIDENTS
ALKALI METALS
BREEDER REACTORS
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HYDROGEN COMPOUNDS
LIQUID METAL COOLED REACTORS
METALS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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