ATWS at Browns Ferry Unit One - accident sequence analysis
This study describes the predicted response of Unit One at the Browns Ferry Nuclear Plant to a postulated complete failure to scram following a transient occurrence that has caused closure of all Main Steam Isolation Valves (MSIVs). This hypothetical event constitutes the most severe example of the type of accident classified as Anticipated Transient Without Scram (ATWS). Without the automatic control rod insertion provided by scram, the void coefficient of reactivity and the mechanisms by which voids are formed in the moderator/coolant play a dominant role in the progression of the accident. Actions taken by the operator greatly influence the quantity of voids in the coolant and the effect is analyzed in this report. The progression of the accident sequence under existing and under recommended procedures is discussed. For the extremely unlikely cases in which equipment failure and wrongful operator actions might lead to severe core damage, the sequence of emergency action levels and the associated timing of events are presented.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7061969
- Report Number(s):
- NUREG/CR-3470; ORNL/TM-8902; ON: TI84014964
- Country of Publication:
- United States
- Language:
- English
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BROWNS FERRY-1 REACTOR
BWR TYPE REACTORS
CONTROL EQUIPMENT
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
MECHANICS
MIXED SPECTRUM REACTORS
PERFORMANCE
PERSONNEL
POWER REACTORS
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
SAFETY
STEAM SYSTEMS
TEMPERATURE DISTRIBUTION
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS