Carbonitride fuel: results of researches

Full text: The method of carbothermic conversation of uranium dioxide in a stream of nitrogen was chosen as a fundamental technology of carbonitride fuel manufacturing. The processes of producing UCN in the presence of methane and carbon oxide were investigated at carbothermic conversion of UO2 in nitrogen and nitrogen-hydrogenous atmospheres (P=0.1 MPa, T=1673-2073 K). The possibility for realization of UCN (UN) synthesis on compact UO2 samples in the presence of gas-phase transfer of carbon in in the system is demonstrated. Results are reported from reactor tests of coated particles and uranium-graphite fuel elements based on carbonitride fuel at temperatures of 1250 deg. C and 1500 deg.C to burnups if 18.5 % fima and 18.0 % fima. respectively. The specimens under test have shown high serviceability of the fuel developed (R/B) no more (3.5-6.0)·10-6). The technology of manufacturing carbonitride (nitride) fuel created in NSC KIPT and the results of its tests, including reactor tests, allow us to recommend it for using in nuclear power plants. The performance of future experiments will make it possible to realize the potential of the developed technology for producing nitride fuel base on nitrogen-15 isotope