Heatup of the TMI-2 lower head during core relocation
Conference
·
OSTI ID:5273148
An analysis has been carried out to assess the potential of a melting attack upon the reactor vessel lower head and incore instrument nozzle penetration weldments during the TMI core relocation event at 224 minutes. Calculations were performed to determine the potential for molten corium to undergo breakup into droplets which freeze and form a debris bed versus impinging upon the lower head as one or more coherent streams. The effects of thermal-hydraulic interactions between corium streams and water inside the lower plenum, the effects of the core support assembly structure upon the corium, and the consequences of corium relocation by way of the core former region were examined. 19 refs., 24 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5273148
- Report Number(s):
- CONF-891103-61; ON: DE90003778
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
054000 -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
CONTAINERS
CORIUM
DECOMMISSIONING
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FLUID FLOW
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HIGH-LEVEL RADIOACTIVE WASTES
HYDRAULICS
HYDRODYNAMICS
JOINTS
LOSS OF COOLANT
MANAGEMENT
MATERIALS
MATHEMATICAL MODELS
MEASURING INSTRUMENTS
MECHANICS
POWER REACTORS
PRESSURE EFFECTS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTOR VESSELS
REACTORS
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SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TEMPERATURE EFFECTS
THERMAL REACTORS
THERMODYNAMICS
THREE MILE ISLAND-2 REACTOR
VERY HIGH TEMPERATURE
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
CONTAINERS
CORIUM
DECOMMISSIONING
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FLUID FLOW
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HIGH-LEVEL RADIOACTIVE WASTES
HYDRAULICS
HYDRODYNAMICS
JOINTS
LOSS OF COOLANT
MANAGEMENT
MATERIALS
MATHEMATICAL MODELS
MEASURING INSTRUMENTS
MECHANICS
POWER REACTORS
PRESSURE EFFECTS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TEMPERATURE EFFECTS
THERMAL REACTORS
THERMODYNAMICS
THREE MILE ISLAND-2 REACTOR
VERY HIGH TEMPERATURE
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS