Station blackout calculations for Browns Ferry
This paper presents the results of calculations performed with the ORNL SASA code suite for the Station Blackout Severe Accident Sequence at Browns Ferry. The accident is initiated by a loss of offsite power combined with failure of all onsite emergency diesel generators to start and load. The Station Blackout is assumed to persist beyond the point of battery exhaustion (at six hours) and without DC power, cooling water could no longer be injected into the reactor vessel. Calculations are continued through the period of core degradation and melting, reactor vessel failure, and the subsequent containment failure. An estimate of the magnitude and timing of the concomitant fission product releases is also provided.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6402578
- Report Number(s):
- CONF-8510173-29; ON: TI86003321
- Resource Relation:
- Conference: 13. water reactor safety research information meeting, Gaithersburg, MD, USA, 22 Oct 1985
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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REACTOR ACCIDENTS
BLACKOUTS
ELECTRIC GENERATORS
HEAT TRANSFER
HYDRAULICS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RISK ASSESSMENT
ACCIDENTS
BWR TYPE REACTORS
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ENERGY LOSSES
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FLUID MECHANICS
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MIXED SPECTRUM REACTORS
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SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
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