[en] An effect of intensive alpha radiation of ²³⁸Pu (content in glass up to 4.0 wt %) on the properties of borosilicate glass (BSG) of the Experimental and Demonstration Center at the Mining and Chemical Combine (EDC MCC) for SNF reprocessing was examined . The characteristics of the BSG were studied immediately after preparing the samples and upon set the dose induced by alpha decays in the sample unit volume (α/cm³). The ²³⁸Pu uniform distribution in the samples was proved by autoradiography and destructive chemical analysis with α-spectrometric ending. The density of the BSG samples was in the range of 2.71 - 2.72 g/cm³ depending on the plutonium content and did not change with time. The ²³⁸Pu leaching rate on the 28th day at 90° C for two parallel glass samples with a cumulative dose of 1.70 × 10¹⁸ α/cm³ was 5.0 × 10^-7 g/(cm² day), which corresponds to the values regulated by the requirements (NP-019-15: Collection, processing, storage, and conditioning of liquid radioactive waste. Safety requirements). The amorphous structure of the sample was preserved at a dose load of 3.2 × 10¹⁸ α/cm³ of glass, its density did not vary, and the surface had a vitreous shine. Defects such as crack, chip, turbidity were not found on them.