The response of BWR Mark III containments to short-term station blackout severe accident sequences
Technical Report
·
OSTI ID:5576488
- Oak Ridge National Lab., TN (USA)
This report describes the results of a series of calculations conducted to investigate the response of BWR Mark 3 containments to short-term station blackout severe accident sequences. The BWR-LTAS, BWRSAR, and MELCOR codes were employed to conduct quantitative accident sequence progression and containment response analyses for several station blackout scenarios. The accident mitigation effectiveness of containment venting and backup emergency power for containment hydrogen ignitors and drywell vacuum breakers is assessed. 18 refs., 142 figs., 12 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5576488
- Report Number(s):
- NUREG/CR-5571; ORNL/TM--11549; ON: TI91015444
- Country of Publication:
- United States
- Language:
- English
Similar Records
The response of BWR Mark II containments to station blackout severe accident sequences
Containment failure time and mode for a low-pressure short-term station blackout in a BWR-4 with Mark-I containment
Vessel failure time for a low-pressure short-term station blackout in a BWR-4
Technical Report
·
Wed May 01 00:00:00 EDT 1991
·
OSTI ID:5535558
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
Vessel failure time for a low-pressure short-term station blackout in a BWR-4
Conference
·
Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5817879
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
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
B CODES
BLACKOUTS
BUILDINGS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CLINTON-1 REACTOR
CLINTON-2 REACTOR
COMBUSTION
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTER PROGRAM DOCUMENTATION
CONTAINERS
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SYSTEMS
CORIUM
DATA COVARIANCES
DETONATIONS
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
FUEL CANS
FUEL ELEMENTS
GRAND GULF-1 REACTOR
GRAND GULF-2 REACTOR
HEAT TRANSFER
HYDRAULICS
HYDROGEN
LOSS OF COOLANT
M CODES
MECHANICS
MELTDOWN
NONMETALS
OXIDATION
PERRY-1 REACTOR
PERRY-2 REACTOR
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RIVER BEND-1 REACTOR
RIVER BEND-2 REACTOR
SAFETY
STEAM
THERMAL REACTORS
THERMOCHEMICAL PROCESSES
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
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
B CODES
BLACKOUTS
BUILDINGS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CLINTON-1 REACTOR
CLINTON-2 REACTOR
COMBUSTION
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTER PROGRAM DOCUMENTATION
CONTAINERS
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SYSTEMS
CORIUM
DATA COVARIANCES
DETONATIONS
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
FUEL CANS
FUEL ELEMENTS
GRAND GULF-1 REACTOR
GRAND GULF-2 REACTOR
HEAT TRANSFER
HYDRAULICS
HYDROGEN
LOSS OF COOLANT
M CODES
MECHANICS
MELTDOWN
NONMETALS
OXIDATION
PERRY-1 REACTOR
PERRY-2 REACTOR
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RIVER BEND-1 REACTOR
RIVER BEND-2 REACTOR
SAFETY
STEAM
THERMAL REACTORS
THERMOCHEMICAL PROCESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS