liquid radioactive waste (LRW)

This paper presents the results of modeling heat fluxes from the outer surface of the KRO-200 container. The study was conducted for a temperature range of 40–150 °C. A comparison of the results was performed for coating materials characterized by different values of emissivity (ε = 0.4–0.95). The total heat release and its components – thermal radiation and convective heat transfer – were calculated. The aim of the study is to evaluate the temperature distribution on the outer surface of the KRO-200 container, which may affect its reliability, leak-tightness and durability.

The process mechanism for sorption of strontium and cesium from liquid radioactive waste using modified bentonites from Yaziv sulfur deposit was investigated. The technique for predicting the intensity of the sorption process based on the comparison of experimental and calculated values of mass transfer coefficients was proposed. It was detected that the process of sorption extraction of strontium and cesium from liquid medium using modified clay minerals may be best described by a three-parameter model of the adsorption isotherms.