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      • The numerical Groundwater Flow Model in Areas of Hydrogeological Windows (for Example Lyubertsy Wastewater Treatment Plant in Moscow)

        ( Irina Kostikova ),( Irina Pozdnykova ) 대한지질공학회 2019 대한지질공학회 학술발표회논문집 Vol.2019 No.2

        The aquifer in coal limestone is a backup source of water supply in Moscow. The horizon lies at a depth of 20-50 m and is separated from the aquifer in Quaternary sediments (upper, shallow) Jurassic clay. There are areas - hydrogeological windows, on which as a result of erosion activity, clay is absent or their thickness decreases to 1-2 m or permeability increases. Since 2013, monitoring of the quality of groundwater has been carried out near large potential sources located on sections of hydrogeological windows. One of these facilities is the Lyubertsy wastewater treatment plant. Lyubertsy wastewater treatment plant in Moscow is the largest in Russia. Analysis of observational data included the establishment of indicators of chemical composition - indicators of the impact of pollution sources on changes in the quality of groundwater; mapping of their distribution over the territory; plotting their changes over time; plotting histograms of their distribution in water samples; cluster and factor analysis of data for the division of wells into groups on the influence of different sources of pollution. The obtained results were used for the variation of the numerical model of groundwater. The numerical groundwater flow model was developed in order to clarify the patterns and mechanisms for the transfer of pollution from the upper horizon to the deeper one at the sites of hydrogeological windows; establishing possible routes of pollutants to the observation wells; pollution forecast. The research was financially supported by the project of the Russian Foundation for Basic Research No. 17-05-01016.

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        Separation and purification of elements from alkaline and carbonate nuclear waste solutions

        Boyarintsev Alexander V.,Stepanov Sergei I.,Kostikova Galina V.,Zhilov Valeriy I.,Safiulina Alfiya M.,Tsivadze Aslan Yu 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.2

        This article provides a survey of wet (aqueous) methods for recovery, separation, and purification of uranium from fission products in carbonate solutions during the reprocessing of spent nuclear fuel and methods for removal of radionuclides from alkaline radioactive waste. The main methods such as selective direct precipitation, ion exchange, and solvent extraction are considered. These methods were compared and evaluated for reprocessing of spent nuclear fuel in carbonate media according to novel alternative non-acidic methods and for treatment processes of alkaline radioactive waste.

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        Reprocessing of simulated voloxidized uranium–oxide SNF in the CARBEX process

        Alexander V. Boyarintsev,Sergei I. Stepanov,Galina V. Kostikova,Valeriy I. Zhilov,Alexander M. Chekmarev,Aslan Yu. Tsivadze 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.7

        The concept of a new method, the CARBEX (CARBonate EXtraction) process, was proposed for reprocessing of spent uranium oxide fuel. The proposed process is based on use of water solutions of Na2CO3 or (NH4)2CO3 and solvent extraction (SE) by the quaternary ammonium compounds for selective recovery and purification of U from the fission products (FPs). Applying of SE allows to reach high degree of purification of U from FPs. Carrying out the processes in poorly aggressive alkaline carbonate media leads to increasing safety of SNF's reprocessing and better selectivity of separation of lanthanides and actinides. Moreover carbonate reprocessing media allows to carry out a recycling and regeneration of reagents. We have been done laboratory scale experiments on the extraction components of simulated voloxidated spent fuel in the solutions of NaOH or Na2CO3–H2O2 and recovery of U from carbonate solutions by SE method using carbonate of methyltrioctylammonium in toluene. It was shown that the purification factors of U from impurities of simulated FPs reached values 103–105. The received results support our opinion that CARBEX after the further development can become more safe, simple and profitable method of spent fuel reprocessing.

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