Problems of Radioactive Graphite Management During Decommissioning of Nuclear Reactors

Abstract

The results of an inspection of samples of the graphite masonry from the RFT research reactor at the National Research Center Kurchatov Institute are presented. These studies made it possible to determine methods and procedures for extracting and packaging the radioactive graphite from the reactor pit during decommissioning. It is shown that management of radioactive graphite requires the development of methods and procedures for determining the radiation characteristics of graphite blocks, first and foremost, the development of highly efficient methods of measuring the specific activity of ¹⁴C. These methods will make it possible to separate radioactive graphite according to the level of contamination and to determine subsequent technologies for handling it during decommissioning of power reactors. It is noted that ¹⁴C can be used as a source of heat.