Effect of small-capacity, high-pressure injection systems on TQUV sequences at Browns Ferry Unit One
Technical Report
·
OSTI ID:5834926
The TQUV (Transient-induced scram, Power Conversion System Unavailable, High Pressure (HPCI, RCIC) and Low Pressure (RHR, Core Spray) injection systems unavailable) accident sequence has been shown to be among the dominant accident sequences in almost all BWR Probabilistic Risk Assessments (PRAs). This report provides an analysis of the ability of the Control Rod Drive (CRD) hydraulic system and the Standby Liquid Control (SLC) system, utilized singly or in combination, to adequately cool the reactor core during this accident sequence. The class of shutdowns considered consists of those initiated by a transient or a loss of off-site power in which there is a successful reactor scram and there is no pipe break. Various combinations of flow delivery capability and operator action are considered and an optimum procedure is recommended. A special version of the MARCH computer code is used to calculate core temperatures and estimate fuel damage for cases involving partial or full core uncovery. The results show that fuel damage can be avoided by appropriate operator action.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5834926
- Report Number(s):
- NUREG/CR-3179; ORNL/TM-8635; ON: DE83017794
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT
AFTER-HEAT REMOVAL
BROWNS FERRY-1 REACTOR
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONTROL
CONTROL ROD DRIVES
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FLOW RATE
FLUID MECHANICS
FLUID POISON CONTROL
HEAT TRANSFER
HYDRAULICS
MECHANICS
MIXED SPECTRUM REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
REMOVAL
SAFETY
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT
AFTER-HEAT REMOVAL
BROWNS FERRY-1 REACTOR
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONTROL
CONTROL ROD DRIVES
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FLOW RATE
FLUID MECHANICS
FLUID POISON CONTROL
HEAT TRANSFER
HYDRAULICS
MECHANICS
MIXED SPECTRUM REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
REMOVAL
SAFETY
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS