BWR reactor vessel bottom head failure modes
Conference
·
OSTI ID:6124656
Boiling water reactors (BWRs) incorporate many unique structural features that make their expected response under severe accident conditions very different from that predicted in the case of pressurized water reactor accident sequences. The effect of the BWR procedural and structural differences upon the progression of a severe accident sequence during the period preceding movement of core debris into the reactor vessel lower plenum has been discussed previously. It is the purpose of this paper to briefly address the events occurring after debris relocation past the core plate and to describe the subsequent expected modes of bottom head pressure boundary failure. As an example, the calculated timing of events for the unmitigated short-term station blackout severe accident sequence at the Peach Bottom Atomic Power Station is also presented. 14 refs., 4 figs., 1 tab.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6124656
- Report Number(s):
- CONF-890546-3; ON: DE89009623
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Conference
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Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6700980
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Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:6343189
Containment failure time and mode for a low-pressure short-term station blackout in a BWR-4 with Mark-I containment
Conference
·
Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:7129195
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
BWR TYPE REACTORS
CONTAINERS
CORIUM
CREEP
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICAL PROPERTIES
MECHANICS
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RUPTURES
SAFETY
STANDARDS
TUBES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
CONTAINERS
CORIUM
CREEP
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICAL PROPERTIES
MECHANICS
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RUPTURES
SAFETY
STANDARDS
TUBES
WATER COOLED REACTORS
WATER MODERATED REACTORS