Electrochemical Decontamination of Irradiated Nuclear Graphite of Uranium-Graphite Nuclear Reactors

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(60)Co,Cs-134,Cs-137,Eu-154, and(241)Am 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(60)Co by a factor of 2-10 and Cs by a factor of 7-100 without gaseous products of reaction being formed.