Common cause failure modelling
Description
Full text: Common cause failure modeling is the best way to communicate the qualitative and quantitative data, required to protect against catalectic failure during normal operation of a nuclear power plant, starting from design phase to decommissioning phase. Also, it is the key to ensure an optimized maintenance and operation all the NPP life-time long under main three principles, concerning: - control and maintenance of nuclear power reactor in all the functioning states; - cooling the reactor core during any transient and normal state; - the radioactivity level inside a guaranteed and fail-safe physical area. The subject of this paper is describing a common cause failure modeling structure. Results and reports of such a modeling could be used to comply with the national regulatory body requirements. Based on numerical values related to the safety analysis, operating and maintaining experience, principles and policies, any activity concerning commercial functioning of a NPP should comprise a good planning and a strong-based safety culture with respect of designer intention. Common cause failure modeling by its screening phase, detailed quantitative and qualitative phase leads to the final goal: operating NPP under reliable and safe conditions. (author)
Availability note (English)
Available from author(s) or Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest - Magurele (RO) or University Politehnica of Bucharest, Splaiul Independentei 313, Sector 6, RO-77206 Bucharest (RO)Additional details
Publishing Information
- Publisher
- Romanian Nuclear Energy Association, AREN
- Imprint Place
- Bucharest (Romania)
- Imprint Title
- International Symposium on Nuclear Energy SIEN 2005, Nuclear Power - A New Challenge. Volume of abstracts
- Imprint Pagination
- 79 p.
- Journal Page Range
- p. 29-30
Conference
- Title
- international symposium on nuclear energy, nuclear power - a new challenge
- Acronym
- SIEN 2005
- Dates
- 23-27 Oct 2005
- Place
- Bucuresti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 37009199
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACTIVITY LEVELS; DATA PROCESSING; FAILURES; LIFETIME; MAINTENANCE; MATHEMATICAL MODELS; REACTOR CONTROL SYSTEMS; REACTOR COOLING SYSTEMS; REACTOR OPERATION; REACTOR SAFETY; REGULATIONS; TRANSIENTS
- Descriptors DEC
- CONTROL SYSTEMS; COOLING SYSTEMS; ENERGY SYSTEMS; LAWS; OPERATION; PROCESSING; REACTOR COMPONENTS; SAFETY
Optional Information
- Notes
- Available in abstract form only, full text entered in this record