Interim reliability evaluation program, Browns Ferry fault trees
Conference
·
OSTI ID:5338941
An abbreviated fault tree method is used to evaluate and model Browns Ferry systems in the Interim Reliability Evaluation programs, simplifying the recording and displaying of events, yet maintaining the system of identifying faults. The level of investigation is not changed. The analytical thought process inherent in the conventional method is not compromised. But the abbreviated method takes less time, and the fault modes are much more visible.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5338941
- Report Number(s):
- CONF-810905-31; ON: DE82007346; TRN: 82-013386
- Resource Relation:
- Conference: ANS/ENS topical meeting on probabilistic risk assessment, Post Chester, NY, USA, 20 Sep 1981
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BROWNS FERRY-1 REACTOR
REACTOR COMPONENTS
RELIABILITY
BROWNS FERRY-2 REACTOR
BROWNS FERRY-3 REACTOR
FAILURES
FAULT TREE ANALYSIS
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
MIXED SPECTRUM REACTORS
POWER REACTORS
REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BROWNS FERRY-1 REACTOR
REACTOR COMPONENTS
RELIABILITY
BROWNS FERRY-2 REACTOR
BROWNS FERRY-3 REACTOR
FAILURES
FAULT TREE ANALYSIS
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
MIXED SPECTRUM REACTORS
POWER REACTORS
REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled