ABSTRACTThe objective of the work was to evaluate the long-term capacity of sintered
glass to retain high-level nuclear wastes (HLW) in near-repository
conditions. We have studied the corrosion behavior of waste forms partially
devitrified (43 vol.%) in different aqueous media. Devitrified samples were
irradiated at doses (γ radiation from a Co 60 source) ranging
from 1.4 × 106 Gy to 2.0 × 108 Gy, in order to study
their aqueous corrosion resistance in simulated underground water. The
results show little or no effect of irradiation on the density,
microstructure and corrosion resistance. The global dissolution rate was
almost constant around a value of 5×10−5 g. cm−2
d−1. Elemental dissolution rates were also unaffected by
radiation.