The relevance of the discussed issue is caused by the need in developing the effective methods for treatment of irradiated graphite of uranium-graphite nuclear reactors in order to reduce the potential danger for further burial in geological formations. The main aim of the study is to develop a method for electrochemical decontamination of graphite radioactive waste in chemically aggressive media and to determine the significant parameters of the process management. The methods: experimental studies of electrochemical treatment of irradiated graphite in various electrolytes and under various conditions. The results. The principal possibility of electrochemical treatment of graphite radioactive waste is shown in the article. The paper introduces the design of the electrolytic cell for carrying out processing and describes the experimental procedure. The authors have analyzed the electrode processes and identified the factors affecting the efficiency of electrochemical deactivation. The dependences of graphite anode destruction rate on the current density and various concentrations of acids are introduced. It was determined that the highest rate of electrode destruction is observed in concentrated hydrochloric acid. The dependence of the removal efficiency of ⁶⁰Co, ^134+137Cs, ¹⁵⁴Eu, ²⁴¹Am on composition of the electrolyte was experimentally obtained. It was found that the maximum degree of decontamination of irradiated nuclear graphite at current density of 0,01 A/cm² and an electrolyte temperature (16–20) °C is achieved in nitric acid with the addition of 0,2 M NaF. The authors carried out the comparative analysis of the experimental results in chemical and electrochemical treatment of graphite radioactive waste. It was shown that electrochemical decontamination of graphite allows reducing the amount of radionuclides ⁶⁰Co by 2–10 times and ¹³⁷Cs by 7–100 times. At the same time, at decontamination, no gaseous reaction products that need to be captured, creating a large amount of secondary radioactive waste, occur.