Station Blackout at Browns Ferry Unit One - accident sequence analysis. Volume 1
This study describes the predicted response of Unit 1 at the Browns Ferry Nuclear Plant to Station Blackout, defined as a loss of offsite power combined with failure of all onsite emergency diesel-generators to start and load. Every effort has been made to employ the most realistic assumptions during the process of defining the sequence of events for this hypothetical accident. DC power is assumed to remain available from the unit batteries during the initial phase and the operator actions and corresponding events during this period are described using results provided by an analysis code developed specifically for this purpose. The Station Blackout is assumed to persist beyond the point of battery exhaustion and the events during this second phase of the accident in which dc power would be unavailable were determined through use of the MARCH code. Without dc power, cooling water could no longer be injected into the reactor vessel and the events of the second phase include core meltdown and subsequent containment failure. An estimate of the magnitude and timing of the concomitant release of the noble gas, cesium, and iodine-based fission products to the environment is provided in Volume 2 of this report. 58 refs., 75 figs., 8 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5450044
- Report Number(s):
- NUREG/CR-2182-Vol.1; ORNL/NUREG/TM-455/V1; ON: TI85015988
- Country of Publication:
- United States
- Language:
- English
Similar Records
Station blackout at Browns Ferry Unit One: iodine and noble-gas distribution and release
Severe-accident-sequence assessment of hypothetical complete-station blackout at the Browns Ferry Nuclear Plant
Related Subjects
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLACKOUTS
BROWNS FERRY-1 REACTOR
BUILDINGS
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
CONTAINERS
CONTAINMENT
CONTAINMENT BUILDINGS
DIESEL ENGINES
ELECTRONIC EQUIPMENT
ENERGY TRANSFER
ENGINES
ENRICHED URANIUM REACTORS
EQUIPMENT
FAILURE MODE ANALYSIS
FAILURES
FISSION PRODUCT RELEASE
FLUID MECHANICS
FUNCTIONS
HEAT ENGINES
HEAT TRANSFER
HYDRAULICS
INTERNAL COMBUSTION ENGINES
MECHANICS
MELTDOWN
MIXED SPECTRUM REACTORS
PERSONNEL
POWER REACTORS
POWER SUPPLIES
REACTOR ACCIDENTS
REACTOR INSTRUMENTATION
REACTOR OPERATORS
REACTOR VESSELS
REACTORS
RESPONSE FUNCTIONS
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS