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This chapter treats self-diffusion, impurity diffusion including fission gas release and release of volatile fission products (Rb, Cs, Br, I, Te), chemical diffusion, thermal diffusion and radiation enhanced diffusion in nuclear fuels. The fuels considered are U and Pu metal and the ceramic fuels including oxides, carbides, nitrides and carbonitrides. Besides experimental results on diffusion processes, calculations of defect energies, diffusion mechanisms and diffusion-related high temperature kinetic processes such as grain growth, creep and sintering, are also considered. In addition, relevant data on ingrowth and thermal recovery of damage-induced defects are presented.

Additional information

Authors: MATZKE H J, JRC Karlsruhe (DE)
Bibliographic Reference: Article: Diffusion Processes in Nuclear Materials (1992) pp. 9-69
Record Number: 199211549 / Last updated on: 1994-11-29
Original language: en
Available languages: en