Residual heat release from HLW and its impact on the DGR’s disposal density

The article presents the calculated possible volume of heat-generating radioactive waste that can be disposed of in a deep disposal facility assuming that the temperature in the bentonite buffer material would not exceed 100 and 125°C FENIA 3D. Version 1.0, i. e., “Software for thermal mode, stress-strain state and strength calculations in radioactive waste disposal facilities” developed by the Nuclear Safety Institute of RAS and certified by Rostekhnadzor was used to perform the calculations. The paper considers three emplacement options for vitrified high-level waste, packages with heat release of 0.6; 1.0 and 2.0 kW/m3.