Debris dispersal from reactor cavities during high-pressure melt ejection accident scenarios
Technical Report
·
OSTI ID:6945270
This report presents the results of a scoping experimental study of the extent of molten debris dispersal from PWR reactor cavities under direct containment heating conditions. Simulated high-pressure melt ejection experiments were conducted using 1/42nd-scale models of reactor cavities and were designed to employ low-temperature melt simulants. Three representative reactor cavities were selected: Zion, Slurry, and Watts Bar. A scaling analysis of the debris dispersal phenomena was carried out and was employed to extrapolate the experimental results for debris dispersal fraction to accident conditions. The experimental results, along with the interpretation based upon the scaling analysis, suggest that the three reactor cavities studied here, i.e., Zion, Surry, and Watts Bar, would retain little, if any, of the melt ejected into them from the reactor vessel following the high-pressure steam blowdown which would follow vessel failure and melt release. 12 refs., 11 figs., 8 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6945270
- Report Number(s):
- NUREG/CR-5146; BNL-NUREG-52147; ON: TI89000228
- Country of Publication:
- United States
- Language:
- English
Similar Records
High pressure melt ejection
An idealized transient model for melt dispersal from reactor cavities during pressurized melt ejection accident scenarios
Pressurized melt ejection into scaled reactor cavities
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5691538
An idealized transient model for melt dispersal from reactor cavities during pressurized melt ejection accident scenarios
Technical Report
·
Sat Jun 01 00:00:00 EDT 1991
·
OSTI ID:5703178
Pressurized melt ejection into scaled reactor cavities
Technical Report
·
Wed Oct 01 00:00:00 EDT 1986
·
OSTI ID:7227238
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
CONTAINMENT
CORIUM
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
I CODES
INFORMATION
MATHEMATICAL MODELS
MECHANICS
MELTDOWN
NUMERICAL DATA
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SCALE MODELS
STRUCTURAL MODELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
CONTAINMENT
CORIUM
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
I CODES
INFORMATION
MATHEMATICAL MODELS
MECHANICS
MELTDOWN
NUMERICAL DATA
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SCALE MODELS
STRUCTURAL MODELS
WATER COOLED REACTORS
WATER MODERATED REACTORS