LONG-TERM INTEGRITY OF BUILDINGS AND SYSTEMS
The present study relates to the conditions of holding nuclear power stations in a safe state after their final shutdown. To assess the reasonable duration of the waiting period before complete dismantling of the installations, it was deemed necessary: - to investigate the causes and consequences of the ageing of a nuclear power station, with particular regard to the safety relevant constituents such as the barriers against the dispersion of contamination; - to evaluate the possible problems of safety, maintenance and decommissioning cost. In the present document, the methodology is developed that is to apply in the particular case of a power station finally shut down which is to be decommissioned and dismantled later. For a detailed exercise of this methodology, the Framatome 900 MWe Pressurized Water Reactor station has been taken as a reference plant. The plan which has been elaborated for this study and for the examination of the technical problems has been conceived so as to suggest to the author of a similar study for a particular power station, all the points he has to consider. One chapter of this document has been devoted to showing the basic differences between the 900 MWe PWR reference plant and the other types of nuclear power station existing in the European Community (e.g., BWR, GCR, FBR) and to identify the consequences concerning the decommissioning and the long-term integrity of the installations.
Bibliographic Reference: EUR 9928 FR (1985), MF, 347 P., BFR 600, BLOW-UP COPY BFR 1735, EUROFFICE, LUXEMBOURG, POB 1003
Availability: Can be ordered online
Record Number: 1989124078600 / Last updated on: 1987-01-01
Available languages: fr