FRANTIC: a computer code for time dependent unavailability analysis
Technical Report
·
OSTI ID:5354891
The FRANTIC computer code evaluates the time dependent and average unavailability for any general system model. The code is written in FORTRAN IV for the IBM 370 computer. Non-repairable components, monitored components, and periodically tested components are handled. One unique feature of FRANTIC is the detailed, time dependent modeling of periodic testing which includes the effects of test downtimes, test overrides, detection inefficiencies, and test-caused failures. The exponential distribution is used for the component failure times and periodic equations are developed for the testing and repair contributions. Human errors and common mode failures can be included by assigning an appropriate constant probability for the contributors. The output from FRANTIC consists of tables and plots of the system unavailability along with a breakdown of the unavailability contributions. Sensitivity studies can be simply performed and a wide range of tables and plots can be obtained for reporting purposes. The FRANTIC code represents a first step in the development of an approach that can be of direct value in future system evaluations. Modifications resulting from use of the code, along with the development of reliability data based on operating reactor experience, can be expected to provide increased confidence in its use and potential application to the licensing process.
- Research Organization:
- Nuclear Regulatory Commission, Washington, D.C. (USA)
- OSTI ID:
- 5354891
- Report Number(s):
- NUREG-0193
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AVAILABILITY
COMPUTER CODES
F CODES
MATHEMATICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROBABILITY
REACTOR COMPONENTS
REACTOR SAFETY
SAFETY
STATISTICS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
TIME DEPENDENCE
220900* -- Nuclear Reactor Technology-- Reactor Safety
AVAILABILITY
COMPUTER CODES
F CODES
MATHEMATICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROBABILITY
REACTOR COMPONENTS
REACTOR SAFETY
SAFETY
STATISTICS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
TIME DEPENDENCE