Abstract
Work has been performed as part of the implementation of measures to reduce the hazard of irradiated graphite during the decommissioning of uranium-graphite nuclear reactors. Electrochemical decontamination is studied as a method of purifying the indicated wastes from radioactive contamination. The results of experiments on removing 60Co,134,137Cs, 154Eu, and 241Am from the surface of irradiated graphite under different conditions are presented. It is shown that electrochemical decontamination of irradiated nuclear graphite in an acidic medium makes it possible to reduce the activity of 60Co by a factor of 2–10 and Cs by a factor of 7–100 without gaseous products of reaction being formed.
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