Rosatom continues its successful research and development efforts to validate innovative nuclear fuels for next-generation fast neutron reactors. Two core designs with different types of uranium-plutonium nuclear fuel are being developed for the BN-1200 reactor: oxide MOX fuel, similar to that used in the BN-800 reactor, and dense nitride SNUP fuel, similar to the fuel designed for the Generation IV BREST-OD-300 reactor. The BREST-OD-300 reactor, which uses a lead coolant, is currently under construction as part of the strategic “Proryv” (“Breakthrough”) industry project.
Significant progress has been made in validating both core designs. For the BN-600 fast reactor at the Beloyarsk NPP, an irradiation assembly (OS-4) with fuel rods based on SNUP fuel has been fabricated. This experimental assembly is designed to achieve a high burnup level that will far exceed the requirements of the reactor core project, incorporating special technical solutions to ensure the safety of testing in the operational reactor.
Additionally, three unique experimental assemblies, KETVS-MAK, have been manufactured with the BN-1200 fuel rods for based on MOX fuel with an axial layer. These assemblies use MOX fuel with an axial blanket, a distinctive feature that sets them apart from traditional MOX fuel. The rods include a segment of "breeding material" within the fuel column, forming a horizontal layer that divides the reactor’s core into two sections. This innovative design significantly reduces radiation damage to the cladding while maintaining the required fuel burnup depth. Although this approach has been studied theoretically in several countries, Russia’s BN-1200 reactor will be the first to implement it in practice.
by Type (HWR, LWR, HTR, FNR, MSR), Application (Power Generation, Desalination, Hydrogen Production, Industrial), Deployment (Single, Multi), Connectivity, Location, Coolant, Power Rating Region
Download free sample pages“The BN-1200 reactor is designed to accommodate either of the two fuel types—SNUP or MOX. We already have extensive experience with MOX fuel production and operation, while high-density SNUP fuel offers additional neutron-physical advantages that could be valuable in the future. We are currently conducting intensive studies to select the optimal core design based on a comprehensive evaluation of multiple parameters,” said Alexander Ugryumov, Senior Vice President for Science and Technology at TVEL JSC.
