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A critical review is given of self-diffusion, impurity diffusion, chemical diffusion, thermal diffusion and radiation-enhanced diffusion in ceramic nuclear fuels, i.e. oxides, carbides, nitrides and carbonitrides of uranium and plutonium. Atomic transport in ThO(2) is also discussed. Experimental results on diffusion, calculations of defect energies, diffusion mechanisms and the relevant data on kinetic processes related to diffusion, ranging from creep, grain growth and sintering to leaching in water are discussed. Recent damage-induced defects and their thermal behaviour using ion implantation of UO(2) and UN with fission products and Rutherford backscattering/channelling techniques are reported and used to discuss the irradiation performance and fission product behaviour in these fuels. Finally, suggestions are made for future work.

Additional information

Authors: MATZKE H J, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: Atomic Mechanisms of Mass Transport in Solids, Oxford (GB), March 29-31, 1989
Availability: Available from (1) as Paper EN 34829 ORA
Record Number: 199010480 / Last updated on: 1994-12-01
Original language: en
Available languages: en