A method for spontaneous formation of a protective coating, consisting of zirconium nitride in a eutectic based on lead with 2.25 mass % magnesium and 0.2 mass % zirconium, on a steel surface is proposed for decreasing the interaction between the sublayer in a fuel element and the fuel-element cladding. It is confirmed on the basis of gravimetric analysis, analysis with a deuteron beam from an EG-2.5 accelerator, x-ray diffraction analysis performed with a DRON-1 diffractometer, and x-ray spectral wave microanalysis that at temperatures in the range 813-1023 K a zirconium nitride coating on the surface of 16Kh12VMSFBR steel will effectively increase the service life of the fuel assemblies in the BREST-OD-300 system (35000 h). The maximum mass loss will be 0.12 kg/m 2 and the maximum thinning a fuel-element wall will be 15 µm.BREST-OD-300 is an experimental sample of a new-generation nuclear power facility with inherent safety [1]. Lead, which has a high boiling point, is chemically inactive, and exhibits low radiation activity, was chosen to remove heat. The low neutron moderation by heavy lead makes it possible to discharge a lattice of fuel elements, compensating the low pump-through rate and high melting temperature of lead.The fuel elements developed for BREST-OD-300 fuel elements consist of pellets fabricated from uranium and plutonium nitride, 16Kh12VMSFBR steel cladding, and a liquid-metal filled gap between the fuel and cladding. Fuel elements with nitride fuel have certain advantages over models used in other systems. The liquid-metal sublayer inside a fuel element makes it possible to decrease the temperature of the nitride fuel to a level that ensures reliable operation of the fuel element with deep burnup and low swelling and low gas-release. The corresponding technology has been developed. The fuel elements have been tested in BOR-60 [2]. The results of the tests performed on a channel with a 43.4 kW fuel assembly, coolant temperature 813 K at the exit into the pump and 888 K at the exit from the fuel assembly in the BOR-60 reactor are presented in [3]. The damaging dose was 6.5 displ./atom and the fuel burnup was 0.44% h.a. No corrosion damage to or unsealing of fuel elements were visible. However, the compatibility of the liquid-metal sublayer inside a fuel element with the fuel-element cladding in the presence of nitride fuel needs further investigation.In the present work, the method of spontaneous formation of a protective coating of zirconium nitride in a lead-based eutectic with 2.25 mass % magnesium and 0.2 mass % zirconium on a steel surface is proposed for decreasing the interac-
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