The Scheme for Optimizing the Liquid Radioactive Waste Management of Ukrainian NPPs
摘要
The optimal scheme of the hypothetical package acceptable for the disposal of salt melt without its processing are considered in detail. It is noted that the main protective barrier during package disposal in a near-surface disposal facility will be a geocement matrix, which can be considered as a promising environment for the immobilization of the liquid salt concentrate or spent filter materials. It is concluded that the use of an insulating geocement barrier is the main condition for forming the package for safe and environmentally friendly disposal of salt melt in near-surface disposal facilities. The given scheme does not require the creation of new equipment at the NPP sites.