Analysis of common cause failures
Description
The aim of the work was to perform research and evaluation of available information. The description concerns both qualitative aspects and quantification of probability of residual common cause failures (CCFs); hence, the effect of those common causes that are not explicitly included in the probabilistic safety assessment (PSA) model is also considered. The issue of CCF description and modelling for a particular PSA study cannot be separated from the particular system modelling style applied. Therefore, an informative chapter was included explaining the style of modelling in a first level PSA study and the issue of inclusion of the various types of dependent failures in the PSA model. The chapter than follows deals with the mathematical models for determining the probability of a CCF. The next part focuses on the analysis of data from the operation of nuclear power plants. (P.A.)
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.czAdditional details
Additional titles
- Original title (Czech)
- Analyza poruch se spolecnou pricinou
Publishing Information
- Imprint Pagination
- [53 p.]
- Report number
- UJV--11380-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 36101202
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- DATA ANALYSIS; FAILURE MODE ANALYSIS; FAILURES; FAULT TREE ANALYSIS; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; POWER REACTORS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- CALCULATION METHODS; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS
Optional Information
- Notes
- 5 tabs., 2 figs., 12 refs.