Methodological approach to the sensitivity analysis of failure effects in modern digital I and C systems - 136
Creators
- 1. Gesellschaft fuer Anlagen- und Reaktorsicherheit -GRS- gGmbH, Schwertnergasse 1, 50667 Cologne (Germany)
Description
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)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 9 p.
Conference
- Title
- 10. International Conference on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies
- Acronym
- NPIC and HIMIT 2017
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52075650
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- 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
- Descriptors DEC
- CONTROL SYSTEMS; MATHEMATICS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; REACTOR LIFE CYCLE; SAFETY; STOCHASTIC PROCESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS
Optional Information
- Notes
- 5 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)