Fragmentation modeling relative to the breakup of molten UO$sub 2$ in sodium
An important aspect of the fuel-coolant interaction problem relative to liquid-metal-cooled fast breeder reactor safety analysis is the fragmentation of molten oxide fuel on contact with liquid-sodium coolant. A proper description of the kinetics of such an event requires an understanding of the breakup process and an estimate of the size and dispersion of such finely divided fuel in the coolant. In recent years, considerable interest has centered on the problem of determining the nature of the fragmentation process. This article reviews both analytic and experimental studies pertaining to such breakup in light of recent developments in the understanding of heat-transfer and solidification phenomena during quenching of UO$sub 2$ in sodium. Where possible, an attempt is made to assess the work potential for fragmentation of the various proposed models and to compare the predicted particle size with experimental results. (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-33-004869
- OSTI ID:
- 4180810
- Journal Information:
- Nucl. Saf., v. 16, no. 6, pp. 688-700, Journal Name: Nucl. Saf., v. 16, no. 6, pp. 688-700; ISSN NUSAA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*LMFBR TYPE REACTORS-- FUEL-COOLANT INTERACTIONS
*URANIUM DIOXIDE-- FRAGMENTATION
220900* --Nuclear Reactor Technology--Reactor Safety
HEAT TRANSFER
MATHEMATICAL MODELS
N77500 --Reactors--Power Reactors
Breeding
N77900* --Reactors--Reactor Safety & Environmental Aspects
PARTICLE SIZE
SODIUM
SOLIDIFICATION