Methodological approach to the sensitivity analysis of failure effects in modern digital I and C systems - 136
- Gesellschaft fuer Anlagen- und Reaktorsicherheit -GRS- gGmbH, Schwertnergasse 1, 50667 Cologne (Germany)
Modern I and C systems of nuclear power plants increasingly use digital equipment, software-based applications for I and C functions and different types and topologies of communication networks as well. The structure, operation and communication of digital safety-related I and C systems are strongly influenced by the implemented automatic fault detection and fault treatment procedures as barriers against failure propagation. Thus, these I and C systems can change their operating states automatically during the operation time, e.g. due to the detection and correction of certain failure types. Reasonably because of these dynamic properties of digital I and C systems the use of classical fault tree and event tree methods solely for the reliability analysis of modern I and C systems is less suitable. These methods basically apply static models and do not consider the temporal changes of the operating state of the I and C system or equipment appropriately. In this paper, a recently developed approach for the sensitivity analysis of digital I and C systems will be introduced that allows to investigate the dynamic behavior of such systems in cases of internal faults and to quantify the effects on the system reliability. The development and testing of the analysis methodology is carried out using models of generic I and C systems with different typical architectures of stepwise increased complexity. (authors)
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23035275
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reliability Assessment of Safety-Critical Network Communication in a Digitalized Nuclear Power Plant
Risk assessment of safety-critical data communication in digital safety feature control system - 205
Related Subjects
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
COMPUTER CODES
CRACK PROPAGATION
DETECTION
FAULT TREE ANALYSIS
MARKOV PROCESS
NUCLEAR POWER PLANTS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR OPERATION
REACTOR SAFETY
RELIABILITY
SENSITIVITY ANALYSIS
TESTING
TOPOLOGY