[en] The objective of the work was to evaluate the long-term capacity of sintered glass to retain the high-level nuclear wastes (HLW) in repository conditions. The SG7 glass containing simulated non-radioactive waste PHWR was irradiated in a Co⁶⁰ γ-field (Division Fuentes Intensas - Centro Atomico Ezeiza) at dose rate of 43.4K Gy/h. We were considered the following potential effects of irradiation: changes in the microhardness and in the density; changes in leaching and dissolution rates at 363 k during 3 days and 28 days, in deionized; changes in the microstructure of the sintered glass forms. Globally we did not find any adverse influence on the bulk corrosion resistance or in the microstructure. We were calculated, by means of the computer code ORIGEN2.1, the fission products activities caused by the high-level wastes from reprocessed spent fuel type PHWR, with a burnup of 7000 MWd/t U and a cooling time of 20 years. We presented the predicted numbers of cumulative gamma events, the activity and the dose due to gamma radiation, per metric to of heavy metal and per cubic centimeter of the sintered HLW glass forms, as a function of the time up to one million years. (author)