Actions for Evaluation of digital fault-tolerant architectures for nuclear power plant control systems [electronic resource].
Evaluation of digital fault-tolerant architectures for nuclear power plant control systems [electronic resource].
- Published
- Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 1990.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (7 pages) : digital, PDF file
- Additional Creators
- Oak Ridge National Laboratory, United States. Office of the Assistant Secretary for Nuclear Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Four fault tolerant architectures were evaluated for their potential reliability in service as control systems of nuclear power plants. The reliability analyses showed that human- and software-related common cause failures and single points of failure in the output modules are dominant contributors to system unreliability. The four architectures are triple-modular-redundant (TMR), both synchronous and asynchronous, and also dual synchronous and asynchronous. The evaluation includes a review of design features, an analysis of the importance of coverage, and reliability analyses of fault tolerant systems. An advantage of fault-tolerant controllers over those not fault tolerant, is that fault-tolerant controllers continue to function after the occurrence of most single hardware faults. However, most fault-tolerant controllers have single hardware components that will cause system failure, almost all controllers have single points of failure in software, and all are subject to common cause failures. Reliability analyses based on data from several industries that have fault-tolerant controllers were used to estimate the mean-time-between-failures of fault-tolerant controllers and to predict those failures modes that may be important in nuclear power plants. 7 refs., 4 tabs.
- Report Numbers
- E 1.99:conf-900607-4
conf-900607-4 - Subject(s)
- Other Subject(s)
- Computer Architecture
- Failure Mode Analysis
- Computerized Control Systems
- Nuclear Power Plants
- Damage
- Design
- Fault Tree Analysis
- Forecasting
- Frequency Analysis
- Human Factors
- Reactor Safety
- Reliability
- Statistical Models
- Synchronization
- Time Dependence
- Tolerance
- Variations
- Control Systems
- Mathematical Models
- Nuclear Facilities
- Power Plants
- Safety
- System Failure Analysis
- Systems Analysis
- Thermal Power Plants
- Note
- Published through SciTech Connect.
01/28/1990.
"conf-900607-4"
"DE90007047"
Advances in human factors research on man-computer interactions: nuclear and beyond, Nashville, TN (USA), 10-15 Jun 1990.
Battle, R.E. - Funding Information
- AC05-84OR21400
View MARC record | catkey: 14361255