Abstract
A lot of work has been already done on helium atomic diffusion in UO 2 samples, but information is still lacking about the fate of helium in high level damaged UOX and MOX matrices and more precisely their intrinsic evolutions under alpha self irradiation in disposal/storage conditions. The present study deals with helium atomic diffusion in actinide doped samples versus damage level. The presently used samples allow a disposal simulation of about 100 years of a UOX spent fuel with a 60 MW d kg −1 burnup or a storage simulation of a MOX spent fuel with a 47.5 MW d kg −1 burnup. For the first time, nuclear reaction analysis of radioactive samples has been performed in order to obtain diffusion coefficients of helium in (U, Pu)O 2. Samples were implanted with 3He + and then annealed at temperatures ranging from 1123 K to 1273 K. The evolution of the 3He depth profiles was studied by the mean of the non-resonant reaction: 3He(d, p) 4He. Using the SIMNRA software and the second Fick’s law, thermal diffusion coefficients have been measured and compared to the 3He thermal diffusion coefficients in UO 2 found in the literature.
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