An idealized transient model for melt dispersal from reactor cavities during pressurized melt ejection accident scenarios
The direct Containment Heating (DCH) calculations require that the transient rate at which the melt is ejected from the reactor cavity during hypothetical pressurized melt ejection accident scenarios be calculated. However, at present no models, that are able to predict the available melt dispersal data from small scale reactor cavity models, are available. In this report, a simple idealized model of the melt dispersal process within a reactor cavity during a pressurized melt ejection accident scenario is presented. The predictions from the model agree reasonably well with the integral data obtained from the melt dispersal experiments using a small scale model of the Surry reactor cavity. 17 refs., 15 figs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5703178
- Report Number(s):
- BNL-46305; ON: DE91015520
- Country of Publication:
- United States
- Language:
- English
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SCALE MODELS
STRUCTURAL MODELS
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SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
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99 GENERAL AND MISCELLANEOUS
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ACCIDENTS
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CONTAINMENT
CORIUM
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
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HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
MELTDOWN
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
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SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
THERMAL POWER PLANTS
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WATER COOLED REACTORS
WATER MODERATED REACTORS