Published April 1996
| Version v1
Report
PSA activities and applications at the Cofrentes NPP
Description
In July 1990 Cofrentes NPP delivered the PSA final report to the Spanish Regulatory Body (Consejo de Seguridad Nuclear). So far the PSA scope included level 1 PSA, internal fire analysis and analyses of internal and external floods. Since then several PSA related activities have been carried out, this paper shows how some of these applications have been performed and presents the results obtained. (author)
Additional details
Publishing Information
- Imprint Title
- Application and development of probabilistic safety assessment for nuclear power plant operations. Report of a technical committee meeting
- Imprint Pagination
- 321 p.
- Journal Page Range
- p. 51-60.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--873
Conference
- Title
- Technical committee meeting on application and development of probabilistic safety assessment for nuclear power plant operations.
- Dates
- 20-23 Sep 1993.
- Place
- Barcelona (Spain).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 27056795
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; COFRENTES REACTOR; FIRES; FLOODS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; RISK ASSESSMENT; SAFETY ANALYSIS
- Descriptors DEC
- BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS