Fault-tree analysis of the EBR-II reactor shutdown system
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7269164
- Argonne National Lab., Upton, NY (United States)
As part of level I Probabilistic Risk Assessment (PRA) of the Experimental Breeder Reactor II (EBR-II), detailed fault trees for the reactor shutdown system are developed. Two classes of transient events that are of particular importance to EBR-II operation and require reactor shutdown are loss of flow (LOF) and transient over power (TOP). Normally in these events, detection channels would automatically open a number of contacts in two redundant shutdown strings. The paper gives the probabilities of scram failure in case of an LOF or TOP. Fault-tree analysis of the EBR-II shutdown system has provided not only a systematic process for calculating the probabilities of system failures but also a useful means for understanding the system and how its components interact during transient events that require shutdown.
- OSTI ID:
- 7269164
- Report Number(s):
- CONF-911107--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANIMALS
BREEDER REACTORS
CALIBRATION
CONTROL ELEMENTS
EBR-2 REACTOR
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
ERRORS
EXPERIMENTAL REACTORS
FAST REACTORS
FAULT TREE ANALYSIS
FBR TYPE REACTORS
HUMAN FACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MAMMALS
MAN
NEUTRON FLUX
OPERATION
PERSONNEL
POWER REACTORS
PRIMATES
PROBABILISTIC ESTIMATION
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTOR OPERATION
REACTOR OPERATORS
REACTOR PROTECTION SYSTEMS
REACTOR SHUTDOWN
REACTORS
RELIABILITY
RESEARCH AND TEST REACTORS
RISK ASSESSMENT
SCRAM
SCRAM RODS
SHUTDOWN
SODIUM COOLED REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TRANSIENT OVERPOWER ACCIDENTS
TRANSIENTS
VERTEBRATES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANIMALS
BREEDER REACTORS
CALIBRATION
CONTROL ELEMENTS
EBR-2 REACTOR
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
ERRORS
EXPERIMENTAL REACTORS
FAST REACTORS
FAULT TREE ANALYSIS
FBR TYPE REACTORS
HUMAN FACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MAMMALS
MAN
NEUTRON FLUX
OPERATION
PERSONNEL
POWER REACTORS
PRIMATES
PROBABILISTIC ESTIMATION
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTOR OPERATION
REACTOR OPERATORS
REACTOR PROTECTION SYSTEMS
REACTOR SHUTDOWN
REACTORS
RELIABILITY
RESEARCH AND TEST REACTORS
RISK ASSESSMENT
SCRAM
SCRAM RODS
SHUTDOWN
SODIUM COOLED REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TRANSIENT OVERPOWER ACCIDENTS
TRANSIENTS
VERTEBRATES