Community Research and Development Information Service - CORDIS


PSA (Probabilistic Safety Assessment) is a good tool to collect, structure and interpret safety-related information, and to identify strong and weak points in the design and operation of a nuclear power plant (NPP). In most of the cases, however, the PSA of a NPP is performed by a group of PSA practitioners that reside far from the plant. The plant operation management team is not directly involved in the PSA development and does not appreciably benefit from it. A living PSA model has to meet the following basic requirements: (i) to represent and structure widely different kinds of information; (ii) to trace the analysis; (iii) for incremental analyses, to update the analyses without losing consistency; (iv) to collect and structure all safety-related expertise and experience in a re-usable form. This paper describes a new approach to safety and reliability analysis and plant modelling that meets all these requirements. In this approach all general and plant specific safety-relevant information is structured in an object-oriented model which can be easily accessed, consulted and modified by the user and from which PSA type results can be obtained.

Additional information

Authors: BESI A, JRC Ispra (IT);POUCET A, JRC Ispra (IT)
Bibliographic Reference: Paper presented: XVIII Annual Meeting of the Spanish Nuclear Society, Puerto de Santa Maria-Jerez (ES), October 28-30, 1992
Availability: Available from (1) as Paper EN 37117 ORA
Record Number: 199310114 / Last updated on: 1994-11-29
Original language: en
Available languages: en