Heatup of the TMI-2 (Three Mile Island Unit 2) lower head during core relocation
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5483967
- Argonne National Laboratory, IL (USA)
According to current perceptions of the Three Mile Island Unit 2 (TMI-2) accident, corium largely relocated into the reactor vessel lower head at {approximately}224 min into the accident. Defueling examinations have revealed that the corium relocated from the molten core region to the lower head predominantly by way of drainage through the core former region (CFR) located between the vertical baffle plates immediately surrounding the fuel assemblies and the core barrel. An analysis has been carried out to assess the heatup of the reactor vessel lower head during the core relocation event, particularly the potential for a melting attack on the lower head wall and the in-core instrument nozzle penetration weldments. The analysis employed the THIRMAL computer code developed at Argonne National Laboratory (ANL) to predict the breakup and quenching or corium jets under film boiling conditions as well as the size distributions and quenching of the resultant molten droplets. The transient heatup and ablation of the vessel wall and penetration weldments due to impinging corium jets was calculated using the MISTI computer code.
- OSTI ID:
- 5483967
- Report Number(s):
- CONF-891103--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 60
- Country of Publication:
- United States
- Language:
- English
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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
ANL
BOILING
COMPUTER CODES
COMPUTERIZED SIMULATION
CORIUM
DRAINAGE
DROPLETS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FILM BOILING
FUEL ASSEMBLIES
HEAT TRANSFER
M CODES
NATIONAL ORGANIZATIONS
PARTICLES
PHASE TRANSFORMATIONS
POWER REACTORS
PWR TYPE REACTORS
QUENCHING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR INTERNALS
REACTORS
SIMULATION
T CODES
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
US AEC
US DOE
US ERDA
US ORGANIZATIONS
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
ANL
BOILING
COMPUTER CODES
COMPUTERIZED SIMULATION
CORIUM
DRAINAGE
DROPLETS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FILM BOILING
FUEL ASSEMBLIES
HEAT TRANSFER
M CODES
NATIONAL ORGANIZATIONS
PARTICLES
PHASE TRANSFORMATIONS
POWER REACTORS
PWR TYPE REACTORS
QUENCHING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR INTERNALS
REACTORS
SIMULATION
T CODES
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS