Abstract

Even in the early 1960's it had already been decided to place high-level radioactive waste in the salt formations of the Federal Republic of Germany. However a major concern is the formation of highly corrosive brines in the event of water filling the repositories. In order to estimate the risks of waste storage in salt repositories it is necessary to investigate the physicochemical properties of the waste materials and of those radionuclides extracted into brine. The extraction of radionuclides from borosilicate glasses or spent fuel elements has been discussed, taking into consideration the two transport mechanisms: diffusion and convection.

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