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In order to provide missing data for storage of actinide containing solidified radioactive waste in deep underground dry geological formations such as salt domes, the tracer diffusion of U-233 was measured in single crystals of NaCl and in actual salt of a repository site (Asse mine in FR Germany). Experiments on interdiffusion between actinide- doped waste glasses and salt were also performed. The mean actinide penetration at the expected maximum temperature of the interface waste matrix/salt in 1.0E6 years is extrapolated to be up to 1 micron for volume diffusion and up to a few microns for grain boundary diffusion.

Additional information

Authors: MATZKE H-J, JRC Karlsruhe (DE);DYMENT F, Comision Nacional de Energia Atomica, Buenos Aires (AR)
Bibliographic Reference: Paper presented: 6th International Conference on Lattice Defects in Ionic Materials, Groningen (NL), Sept. 3-8, 1990
Availability: Available from (1) as Paper EN 35464 ORA
Record Number: 199011601 / Last updated on: 1994-12-02
Original language: en
Available languages: en
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