Features of applying safeguards to Optimized Floating Power Unit spent nuclear fuel handling

Abstract

After the Floating Power Unit Akademik Lomonosov with the KLT-40S reactor plant had been successfully commissioned, the next step for ROSATOM was to develop optimized floating power units (OFPU). OFPUs powered by the RITM reactor plant are an export-oriented product, and they designed to operate on sites outside Russia. OFPU engineering solutions are based upon the practical design and operation experience in nuclear-powered icebreakers and upon problem solving to assure safety for operation of nuclear plants under severe northern conditions. At the nuclear fuel enrichment lower than 20%, the refueling interval for the OFPU may be up to 10 years depending on Loadings. The RITM reactor refueling process has a number of differences compared to the refueling process of other nuclear power plants fitted with water-cooled water-moderated power reactors. RITM plants have never been placed under the IAEA Safeguards, and capabilities and features of applying the IAEA Safeguards to such plants require an additional analysis. The developed operation model assumes that the OFPU be operated on a deployment site for a long period, and all fuel handling operations will be done at a specialized facility in the Russian Federation (RF). This paper is discussing the major fuel handling features in the life cycle of the OFPU fitted with RITM-200M—these are the critical features in terms of the IAEA Safeguards. Also, the paper is providing the designers’ perspective on solving the key non-proliferation problems through adapting the Safeguards approaches with account of the OFPU technical features.