Swelling of Intermetallic Uranium–Silumin Dispersion Fuel Composition in Experimental Fuel Rods of the SM Reactor

Experimental dispersion fuel rods with intermetallic uranium–silumin fuel composition, proposed for the modernized core of the SM reactor, were investigated. The conditions for reactor testing of fuel rods are modeled in such a way that different burnup levels and heat flux densities are achieved in them. It was shown that the reactor testing conditions determine the swelling of the fuel meat and other resource characteristics of fuel rods. For irradiation parameters no higher than average, the dispersion structure and performance of the fuel composition are preserved and swelling is due to solid products of fission. At the maximum parameters, the components of the composition underwent intense interactions – significant swelling and loss of functionality. The permissible parameters for the operation of fuel rods with an intermetallic uranium–silumin composition and higher performance limits can be elaborated in additional investigations and modifications.