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Requirements for Waste Packages for heat generating radioactive waste and spent nuclear fuel elements in rock salt, clay stone and crystalline rock

POLLUX-cask in maintenance station

The main objective of the R&D-Project KoBrA, which DBE TECHNOLOGY performs together with the BAM (Bundesanstalt für Materialforschung und-prüfung) on behalf of BMWi and PTKA, is to derive requirements for waste packages for heat generating radioactive waste and spent nuclear fuel elements and to develop waste package concepts. Existing legislation and technical guidelines will be considered as well as international state of the art on existing sets of requirements and technical concepts. And of course the waste packages must provide a safe encapsulation of the radioactive waste and spent nuclear fuel during repository operation on surface and underground, but have to provide safe enclosure in the long-term as well. End of the year 2019, at the end of the project, suggestions for the technical implementation of the requirements by means of generic waste package concepts have to be provided as well as assessments of the implications of design decisions on the design of the entire repository system. If a waste package type like the POLLUX®-cask which was developed for a repository in salt will be kept has to be analyzed.

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