Failure mode analysis using state variables derived from fault trees with application
Conference
·
OSTI ID:6238023
Fault Tree Analysis (FTA) is used extensively to assess both the qualitative and quantitative reliability of engineered nuclear power systems employing many subsystems and components. FTA is very useful, but the method is limited by its inability to account for failure mode rate-of-change interdependencies (coupling) of statistically independent failure modes. The state variable approach (using FTA-derived failure modes as states) overcomes these difficulties and is applied to the determination of the lifetime distribution function for a heat pipe-thermoelectric nuclear power subsystem. Analyses are made using both Monte Carlo and deterministic methods and compared with a Markov model of the same subsystem.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6238023
- Report Number(s):
- LA-UR-81-2595; CONF-810905-5; ON: DE81030239
- Country of Publication:
- United States
- Language:
- English
Similar Records
State variable method of fault tree analysis
Use of Fault Tree Analysis for Automotive Reliability and Safety Analysis
Systems analysis approach to probabilistic modeling of fault trees
Technical Report
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:5265359
Use of Fault Tree Analysis for Automotive Reliability and Safety Analysis
Conference
·
Wed Sep 24 00:00:00 EDT 2003
·
OSTI ID:15006932
Systems analysis approach to probabilistic modeling of fault trees
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5697527
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210600* -- Power Reactors
Auxiliary
Mobile Package
& Transportable
COUPLING
DIRECT ENERGY CONVERTERS
FAILURE MODE ANALYSIS
FAULT TREE ANALYSIS
HEAT PIPES
MARKOV PROCESS
MOBILE REACTORS
MONTE CARLO METHOD
NESDPS Office of Nuclear Energy Space and Defense Power Systems
POWER REACTORS
REACTORS
RELIABILITY
SPACE POWER REACTORS
STOCHASTIC PROCESSES
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMOELECTRIC GENERATORS
210600* -- Power Reactors
Auxiliary
Mobile Package
& Transportable
COUPLING
DIRECT ENERGY CONVERTERS
FAILURE MODE ANALYSIS
FAULT TREE ANALYSIS
HEAT PIPES
MARKOV PROCESS
MOBILE REACTORS
MONTE CARLO METHOD
NESDPS Office of Nuclear Energy Space and Defense Power Systems
POWER REACTORS
REACTORS
RELIABILITY
SPACE POWER REACTORS
STOCHASTIC PROCESSES
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMOELECTRIC GENERATORS