Cleanup Cycle Model of Uranyl Nitrate Solution Fuel of Isotope Production System

Isotope production using homogeneous solution fuel reactor has more benefits than the classical method by irradiation of uranium sample in the non power reactor. Several short lives isotopes could be extracted directly from the solution fuel. An aqueous homogeneous reactor (AHR) has advantages that it need less fissile uranium; produce less radioactive waste than other existing isotope production methods. The main parts of the production system are AHR, extraction facility and solution fuel cleanup facility. Both extraction and cleanup facilities have influence on the concentration of several nuclides. Assessment of several cleanup cycle models has been developed in this work. The efficiencies of separations during isotope extraction and fuel cleanup were assumed constant. Assessment of fuel cycle cleanup model could be very useful to track fissile and other specific nuclides. This ability may be valuable for design of safeguards, safety and security systems. It should be ensured that no plutonium separation on the stripping process with the total plutonium iventory less than sigficant quantity 8 kg and production rate less than 100 g per year. A safeguard system should be integrated on the facility design.