Methodology of containment response analysis for the Probabilistic Safety Assessment -PSA of the CAREM-25 nuclear power plant
- 1. Universidad Nacional de Cuyo, Mendoza (Argentina). Facultad de Ingenieria. Centro de Estudios de Ingenieria Asistida por Computadora
Description
This work is part of the Probabilistic Safety Assessment actually under development for the CAREM-25 Nuclear Power Station, and departs from the accident sequences already obtained and quantified by the Event Trees/Fault Trees techniques. At first, the potential containment failure modes for nuclear stations are listed, based on the experience. Then, the CAREM-25 design peculiarities are analyzed, on their possible influence on the containment behavior during, severe accidents. Then Plan Damage States are then defined. Furthermore, Containment Damage States are also defined, and Containment Event Trees are built for each Plant Damage State. Those sequences considered representative from the annual probability (those which exceed or equal a probability of 1E-09 per year, are used to quantify the combinations of Plant Damage States/Containment Damage States, based on the estimation of a Vulnerability Matrix. (author)
Availability note (English)
Available from the library of the Brazilian Nuclear Energy Commission, Rio de JaneiroAdditional details
Additional titles
- Original title (Spanish)
- Metodologia de analisis de la respuesta de contencion para el APS en la Central CAREM-25
Publishing Information
- Imprint Pagination
- 6 p.
Conference
- Title
- 6. General congress on nuclear energy
- Original Conference Title
- 6. Congresso geral de energia nuclear
- Dates
- 27 Oct - 1 Nov 1996
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 31026944
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONTAINMENT SYSTEMS; DESIGN; FAILURE MODE ANALYSIS; FAULT TREE ANALYSIS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; SAFETY ANALYSIS
- Descriptors DEC
- CONTAINMENT; ENGINEERED SAFETY SYSTEMS; NUCLEAR FACILITIES; POWER PLANTS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS
Optional Information
- Notes
- 2 refs., 14 figs., 2 tabs.