Published 1996 | Version v1
Miscellaneous

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 Janeiro

Additional 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.