Heatup of the TMI-2 lower head during core relocation

Conference · Sun Jan 01 00:00:00 EST 1989

OSTI ID:5273148

Wang, S K; Sienicki, J J; Spencer, B W

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; TRN: 90-000949
• Resource Relation: Conference: Winter meeting of the American Nuclear Society, San Francisco, CA (USA), 26-30 Nov 1989
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
THREE MILE ISLAND-2 REACTOR
RADIOACTIVE WASTE DISPOSAL
CORIUM
DECOMMISSIONING
FAILURE MODE ANALYSIS
FLUID FLOW
HEAT FLUX
HEAT TRANSFER
HIGH-LEVEL RADIOACTIVE WASTES
HYDRAULICS
HYDRODYNAMICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MEASURING INSTRUMENTS
PRESSURE EFFECTS
REACTOR CORES
REACTOR SAFETY
REACTOR VESSELS
TEMPERATURE EFFECTS
THERMODYNAMICS
VERY HIGH TEMPERATURE
WELDED JOINTS
ACCIDENTS
CONTAINERS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
JOINTS
MANAGEMENT
MATERIALS
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
054000 - Nuclear Fuels- Health & Safety
990200 - Mathematics & Computers