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Feasibility of Processing of Accumulated Liquid Radioactive Waste from BN-350 Reactor

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Radiochemistry Aims and scope

Abstract

It was found that the filtrate yielded by passing bottoms decantates through selective sorbents has the volume activity with respect to 137Cs and 60Co significantly greater than DKb. A pretreatment of the bottoms before selective sorption was tested, which consisted in ozonation and subsequent filtration of the resulting precipitate. By the example of the liquid radioactive waste (LRW) decantate with the highest volume activity, it was shown that by combining the pretreatment with selective sorption it was possible to remove 137Cs, 60Co, and 54Mn radionuclides from the decantate to the level under DKb. Cementation of the slurries in the slurry/cement ratio of 0.3-0.7 was tested. It was proposed that the decantate freed from radionuclides be discharged into the Caspian Sea, and the slurry and secondary wastes yielded by decantate decontamination be included into cement compound.

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Savkin*, A.E., Slastennikov, Y.T., Sinyakin, O.G. et al. Feasibility of Processing of Accumulated Liquid Radioactive Waste from BN-350 Reactor. Radiochemistry 43, 311–314 (2001). https://doi.org/10.1023/A:1012877028805

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  • DOI: https://doi.org/10.1023/A:1012877028805

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