The SR 97 Safety Analysis was published in 1999; a leaflet that summarizes the report on this analysis can be ordered from SKB.
The aims of SR 97
The principal aims of SR 97 were:
- To find out whether very long-term safe final disposal of spent nuclear fuel is possible in Swedish bedrock
- To demonstrate the methodology upon which the safety analysis was based.
The calculations in SR 97 are based on a detailed description of the system, measurement data from three actual sites and five different scenarios. The results show that the prerequisites are good for storing spent nuclear fuel in a final repository in Swedish bedrock.