A computer code for common-cause failure analysis
Creators
- 1. Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)
Description
COMCAF, a computer code for the common-cause failure analysis, is developed to treat the common-cause failures in nuclear power plants. In the treatment of common-cause failures, the minimal cut sets of the system are obtained first without changing the fault-tree structure. The occurrence probabilities of the minimal cut sets are then calculated accounting for the common-cause failures between components in the same and/or in the different minimal cut sets. The basic parameter model is used to model the common-cause failures between similar or identical components. The top event probability is evaluated using the inclusion-exclusion method. This study applied this common-cause failure analysis to the PWR auxiliary feedwater system. The results in the top event probability for the system are compared with those of no common-cause failures
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- 607 p.
- Journal Page Range
- p. 341-346
Conference
- Title
- 1991 spring meeting of the KNS
- Dates
- 24-25 May 1991
- Place
- Taejon (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 38009046
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- C CODES; FAILURES; FEEDWATER; NUCLEAR POWER PLANTS; PROBABILITY; PWR TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 4 tabs