International audienceThis investigation concerns borosilicate glass leaching mechanisms and the evolution of alteration layer under electron beam irradiation. A simple glass doped with rare earth elements was selected in order to access mechanistic and structural information and better evaluate the effects of irradiation. It was fully leached in initially pure water at 90 °C and at high glass surface area to solution volume ratio (S/V = 20 000 m−1) in static conditions. Under these conditions, the system quickly reaches the residual alteration rate regime. A small particle size fraction (2–5 μm) was sampled in order to obtain a fairly homogeneous altered material enabling the use of bulk characterization methods. External irradiations with...
Fission products and minor actinides are currently immobilized by vitrification in a borosilicate gl...
The present experiments with Savannah River Plant simulated nuclear waste glass implanted with Pb io...
The long-term behavior of high-level nuclear glass subjected to alpha/beta radiation by long-life ra...
International audienceThis investigation concerns borosilicate glass leaching mechanisms and the evo...
This work addresses the impact of radiation damage on the leaching of International Simple Glass (IS...
International audienceThis work addresses the impact of radiation damage on the leaching of internat...
International audienceSeveral countries have chosen the recycling of U and Pu in MOX fuels associate...
The residual rate regime of SON68 nuclear glass has been investigated here by static experiments und...
AbstractFission products and minor actinides arising from spent fuel reprocessing are immobilized in...
Les déchets nucléaires de haute activité, produits en France sous forme de colis de verre lors du tr...
International audienceAs borosilicate glasses are used in many countries to immobilize fission produ...
International audienceThe alteration of a four-oxide alumino-borosilicate glass close to ISG was stu...
ACELnYSiAlO glasses (Ln=La or Ce) are considered as potential matrices for the specific storage of m...
Leaching behavior is the major waste characteristic that is critical for a long-term assessment prio...
Fission products and minor actinides are currently immobilized by vitrification in a borosilicate gl...
The present experiments with Savannah River Plant simulated nuclear waste glass implanted with Pb io...
The long-term behavior of high-level nuclear glass subjected to alpha/beta radiation by long-life ra...
International audienceThis investigation concerns borosilicate glass leaching mechanisms and the evo...
This work addresses the impact of radiation damage on the leaching of International Simple Glass (IS...
International audienceThis work addresses the impact of radiation damage on the leaching of internat...
International audienceSeveral countries have chosen the recycling of U and Pu in MOX fuels associate...
The residual rate regime of SON68 nuclear glass has been investigated here by static experiments und...
AbstractFission products and minor actinides arising from spent fuel reprocessing are immobilized in...
Les déchets nucléaires de haute activité, produits en France sous forme de colis de verre lors du tr...
International audienceAs borosilicate glasses are used in many countries to immobilize fission produ...
International audienceThe alteration of a four-oxide alumino-borosilicate glass close to ISG was stu...
ACELnYSiAlO glasses (Ln=La or Ce) are considered as potential matrices for the specific storage of m...
Leaching behavior is the major waste characteristic that is critical for a long-term assessment prio...
Fission products and minor actinides are currently immobilized by vitrification in a borosilicate gl...
The present experiments with Savannah River Plant simulated nuclear waste glass implanted with Pb io...
The long-term behavior of high-level nuclear glass subjected to alpha/beta radiation by long-life ra...