Loss of DHR sequences 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 loss of decay heat removal (DHR) capability following scram from full power with the power conversion system unavailable. In accident sequences without DHR capability, the residual heat removal (RHR) system functions of pressure suppression pool cooling and reactor vessel shutdown cooling are unavailable. Consequently, all decay heat energy is stored in the pressure suppression pool with a concomitant increase in pool temperature and primary containment pressure. With the assumption that DHR capability is not regained during the lengthy course of this accident sequence, the containment ultimately fails by overpressurization. Although unlikely, this catastrophic failure might lead to loss of the ability to inject cooling water into the reactor vessel, causing subsequent core uncovery and meltdown. The timing of these events and the effective mitigating actions that might be taken by the operator are discussed in this report.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6168063
- Report Number(s):
- NUREG/CR-2973; ORNL/TM-8532; ON: DE83012314
- Resource Relation:
- Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Severe-accident-sequence assessment of hypothetical complete-station blackout at the Browns Ferry Nuclear Plant
Fission product transport analysis in a loss of decay heat removal accident at Browns Ferry
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BROWNS FERRY-1 REACTOR
REACTOR ACCIDENTS
RHR SYSTEMS
AFTER-HEAT REMOVAL
COMPUTER CALCULATIONS
CONTAINMENT SYSTEMS
FAILURES
HEAT TRANSFER
HYDRAULICS
PRESSURE GRADIENTS
PRESSURE SUPPRESSION
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
BWR TYPE REACTORS
CONTAINMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MECHANICS
MIXED SPECTRUM REACTORS
POWER REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled