Development of a process for treatment and solidification of liquid radioactive concentrates from the Leipunskii Institute of Energy Physics

Treatment of liquid radioactive concentrates (LRCs) from the Leipunskii Institute of Energy Physics using Termoksid-35 ferrocyanide sorbent was studied. After passing LRC with a volume activity of 3.9 × 10 8 Bq l −1 through a column packed with the sorbent, the volume activity of the filtrate does not exceed 3.7 × 10 4 Bq l −1 . The LRC decontaminated from the major amount of radionuclides is fed to cementation. A formulation of a cement compound with a polyfunctional additive consisting of finely dispersed cement, bentonite clay, biocidal additive, plasticizer, and defoamer was developed. For the storage of a container filter with the spent ferrocyanide sorbent, it is suggested to place it in a 1 m 3 metallic container in which the cement compound with the LRC decontaminated from the major fraction of cesium acts as biological protection. The γ-radiation dose rate from the 1 m 3 container filled with the cement compound, with the filter with the spent sorbent placed inside, was calculated. A technology for processing of liquid radioactive concentrates from the Leipunskii Institute of Energy Physics was suggested and substantiated.