Severe Accident Sequence Analysis Program: Anticipated transient without scram simulations for Browns Ferry Nuclear Plant Unit 1
An analysis of five anticipated transients without scram (ATWS) was conducted at the Idaho National Engineering Laboratory (INEL). The five detailed deterministic simulations of postulated ATWS sequences were initiated from a main steamline isolation valve (MSIV) closure. The subject of the analysis was the Browns Ferry Nuclear Plant Unit 1, a boiling water reactor (BWR) of the BWR/4 product line with a Mark I containment. The simulations yielded insights to the possible consequences resulting from a MSIV closure ATWS. An evaluation of the effects of plant safety systems and operator actions on accident progression and mitigation is presented.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6370654
- Report Number(s):
- NUREG/CR-4165; EGG-2379; ON: TI87010676
- Country of Publication:
- United States
- Language:
- English
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INEL BWR severe accidnet ATWS study
ATWS analysis for Browns Ferry Nuclear Plant Unit 1
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Conference
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Sat Jan 01 00:00:00 EST 1983
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OSTI ID:6370654
ATWS analysis for Browns Ferry Nuclear Plant Unit 1
Conference
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Tue Jan 01 00:00:00 EST 1985
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OSTI ID:6370654
Severe Accident Sequence Analysis (SASA) Program sequence event tree: boiling water reactor anticipated transient without scram
Technical Report
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Sun Apr 01 00:00:00 EST 1984
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OSTI ID:6370654
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BROWNS FERRY-1 REACTOR
ATWS
REACTOR SAFETY
C CODES
COMPUTERIZED SIMULATION
CONTAINMENT
EMERGENCY PLANS
FAILURE MODE ANALYSIS
HEAT TRANSFER
R CODES
RADIOACTIVE EFFLUENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR OPERATORS
RISK ASSESSMENT
S CODES
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
MATERIALS
MIXED SPECTRUM REACTORS
OPERATION
PERSONNEL
POWER REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR ACCIDENTS
REACTORS
SAFETY
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BROWNS FERRY-1 REACTOR
ATWS
REACTOR SAFETY
C CODES
COMPUTERIZED SIMULATION
CONTAINMENT
EMERGENCY PLANS
FAILURE MODE ANALYSIS
HEAT TRANSFER
R CODES
RADIOACTIVE EFFLUENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR OPERATORS
RISK ASSESSMENT
S CODES
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
MATERIALS
MIXED SPECTRUM REACTORS
OPERATION
PERSONNEL
POWER REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR ACCIDENTS
REACTORS
SAFETY
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled