Failure modes analysis for BWR Mark-2 in-pedestal dry-well drain pipes
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5763668
- Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)
- Rensselaer Polytechnic Inst., Troy, NY (United States)
Several boiling water reactor (BWR) Mark-2 containment dry wells include drain pipes that penetrate the concrete pedestal floor and lead into the wet-well region. For example, these pipes are installed in the Limerick, LaSalle, and WNP-2 BWR plants. During severe-accident melt progression events, these penetrations might provide pathways for the rapid relocation of molten corium out of the in-pedestal region, and the passive suppression capability of the containment may be lost. Early pressure suppression pool bypass could also lead to detrimental effects if containment venting were employed. Analyses of this issue were conducted by the US Nuclear Regulatory Commission's BWR Mark-2 and -3 parametrics program at Oak Ridge National Laboratory. The results of these analyses are presented in this paper.
- OSTI ID:
- 5763668
- 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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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
BUILDING MATERIALS
BWR TYPE REACTORS
BYPASSES
CHALCOGENIDES
CONCRETES
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CORIUM
DRAINAGE
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATERIALS
MECHANICS
METALS
NATIONAL ORGANIZATIONS
ORNL
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE
PIPES
POWER REACTORS
PRESSURE SUPPRESSION
PRESSURE VESSELS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
RUPTURES
SAFETY
THERMAL REACTORS
TRANSITION ELEMENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
BUILDING MATERIALS
BWR TYPE REACTORS
BYPASSES
CHALCOGENIDES
CONCRETES
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CORIUM
DRAINAGE
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATERIALS
MECHANICS
METALS
NATIONAL ORGANIZATIONS
ORNL
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE
PIPES
POWER REACTORS
PRESSURE SUPPRESSION
PRESSURE VESSELS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
RUPTURES
SAFETY
THERMAL REACTORS
TRANSITION ELEMENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM