The PSA programme in VUPEX Bratislava
Description
The areas in which VUPEX is active reflect problems arising in the nuclear power plant operation. Main field of activities are systems analyses which include reliability analyses of safety systems, probabilistic safety assessment and fire protection for WWER 440s. The system reliability analyses are concentrated on the front-line and support systems of V213 and V230 type reactors. Examples are the high pressure safety system and reactor building spray system of V230 type reactors and numerous single system studies sponsored by utility for design, review and reconstruction purposes. The fault tree method by TREE MASTER code has been used for analyses. VUPEX performs research into Probabilistic Safety Assessment within the Level 1 PSA study of the unit 1 of Dukovany Nuclear Power Plant. The work was started in 1989 and the Level 1 study will be finished in 1993. The systems analysed in VUPEX are those V213 type front-line systems identified in event trees. Also analysed are the support systems whose action is required by the front-line systems during the course of an accident. The RISK SPECTRUM-PSA code is used for analyses. (author)
Additional details
Publishing Information
- Imprint Title
- Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors
- Imprint Pagination
- 264 p.
- Journal Page Range
- p. 71-72.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--737
Conference
- Title
- Technical committee meeting on advances in reliability analysis and probabilistic safety assessment for nuclear power reactors.
- Dates
- 7-11 Sep 1992.
- Place
- Budapest (Hungary).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 25037043
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAULT TREE ANALYSIS; FIRE PREVENTION; PROBABILISTIC ESTIMATION; R CODES; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS; SUPPORTS; T CODES; WWER-3 REACTOR
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; MECHANICAL STRUCTURES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS