Simulation of the Processes of Gamma-Radiation Transport through Shielding Containers for Radioactive Waste

摘要

Considerable amounts of solid radioactive waste (SRW) with low and intermediate levels of radioactivity produced by operating atomic power stations (APS) and during liquidation of nuclear accidents and research work must be safely utilized. To increase the level of safety during subsequent long-term SRW storage or burial, they are stabilized by incorporation into cement matrices [1-3].