| 摘要 |
Spent fuel elements from a nuclear power station are inserted into an internal container which is in turn seated in an outer transport and temporary storage container which shields the radiation and effectively conducts the heat away. The containers placed into one another are transported to a temporary store and temporarily stored there. After a decay time of a few years, the inner container is taken out and either, if it is corrosion-resistant under the environmental conditions prevailing in a salt dome, directly or in a corrosion-resistant ultimate storage container, into which it has been transferred in the temporary store, transported to the ultimate storage location and ultimately stored. A container for the transport and/or the storage of spent fuel elements is manufactured using a container shell material which has properties shielding radioactive radiation and good thermal conductivity properties and which is a hydraulically setting dry mass consisting of non-corroding constituents which in particular are resistant to acidic vapours and solutions which arise in salt domes serving for ultimate storage.
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