Thermal behavior of molten corium during TMI-2 core relocation event
Conference
·
OSTI ID:6161525
During the TMI-2 accident, a pool of molten corium formed in the central region of the core and was contained by solidified crusts. Failure of the crust surrounding the molten material, at approximately 224 min, resulted in a relocation of an estimated 20-25 tons of molten corium through peripheral fuel assemblies in the east side of the vessel, as well as through the core barrel assembly (CBA) at the periphery of the core. This paper presents the results of an analyses carried out to investigate the thermal interactions of molten corium with the CBA structures during the relocation event. The principal objectives of the analyses are: (a) to assess the potential for relocation to take place through the CBA versus the flow of molten core material directly downward through the core via the fuel assemblies; and (b) to understand the distribution of prior molten corium observed during vessel defueling examinations. 5 refs., 1 fig.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA); Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6161525
- Report Number(s):
- CONF-881011-38; ON: DE89007499
- Country of Publication:
- United States
- Language:
- English
Similar Records
Heatup of the TMI-2 (Three Mile Island Unit 2) lower head during core relocation
Heatup of the TMI-2 lower head during core relocation
Coupled thermomechanical response of a pressure vessel lower head to relocated corium
Conference
·
Tue Oct 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5483967
Heatup of the TMI-2 lower head during core relocation
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:5273148
Coupled thermomechanical response of a pressure vessel lower head to relocated corium
Conference
·
Thu Nov 30 23:00:00 EST 1995
·
OSTI ID:131852
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
CORIUM
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
MELTDOWN
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
THERMAL ANALYSIS
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
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
CORIUM
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
MELTDOWN
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
THERMAL ANALYSIS
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS