Cooling of core debris within the reactor vessel lower head
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5854481
- Fauske and Associates, Inc., Burr Ridge, IL (United States)
- Commonwealth Edison Co., Downers Grove, IL (United States)
Under severe-accident conditions, the most crucial action for recovery from the accident state is to cool the core debris and prevent or terminate attack on the remaining fission product barriers. One means of preventing attack on the containment structures is to retain the core debris within the reactor vessel. The Three Mile Island Unit 2 (TMI-2) accident demonstrated that this could be accomplished by water resident within the reactor vessel combined with injection on a continual basis to quench the debris and remove decay heat over the long term. Some accident situations could result in the transport of molten core debris to the lower plenum, as occurred in TMI-2, the boil-off of water in the lower plenum, and an inability to add water to the reactor coolant system (RCS). Even in this extreme set of circumstances, sufficient cooling may be available to prevent failure of the reactor pressure vessel (RPV) lower head and thereby retain the core debris within the vessel. Experiments were performed in support of Commonwealth Edison's Zion individual plant examination and accident management programs that demonstrate nucleate boiling heat removal rates from the outer surface of a simulated RPV lower head surrounded by typical reflective insulation used in nuclear power plants.
- OSTI ID:
- 5854481
- Report Number(s):
- CONF-910603--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
- Country of Publication:
- United States
- Language:
- English
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Cooling of core debris within the reactor vessel lower head
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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210200 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
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AFTER-HEAT REMOVAL
BOILING
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ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
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FISSION PRODUCTS
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
ISOTOPES
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MITIGATION
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PHASE TRANSFORMATIONS
POWER REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
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RISK ASSESSMENT
SAFETY
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
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WATER MODERATED REACTORS
ZION-1 REACTOR
ZION-2 REACTOR
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
BOILING
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
CORIUM
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FILM BOILING
FISSION PRODUCTS
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
ISOTOPES
MANAGEMENT
MATERIALS
MECHANICS
MITIGATION
NUCLEATE BOILING
PHASE TRANSFORMATIONS
POWER REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
REMOVAL
RISK ASSESSMENT
SAFETY
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZION-1 REACTOR
ZION-2 REACTOR