Analysis of the Effectiveness of Fuel Composition Changing in a Pulse Fast-Neutron Research Reactor
3/27/2026 2026 - #01 Application of nuclear tech
https://doi.org/10.26583/npe.2026.1.13
UDC: 621.039.5
In this paper, we will analyze the optimal design of the high-flux pulse periodic neutron source and further develop the concept of a pulse fast reactor with neptunium-nitride fuel. Since it is planned to increase the neutron flux density of the new neutron source by an order of magnitude in comparison with IBR-2M, the main goal of the work is to evaluate the current design of the reactor construction and possible options for modifying its concept. At the same time, the design features of the reactor must be justified from the point of view of its safe operation. Based on the computational simulation of the reactor, the main neutron characteristics and tallies of the facility were obtained. Thus, the main advantages and disadvantages of the reactor with neptunium-nitride fuel were identified and relevant solutions for changing the design were proposed. The principles of designing and optimizing a periodic pulse reactor using innovative types of nuclear fuel are discussed. For example, promising uranium-plutonium fuels were used as fuel, the modulator material was changed to a more suitable one for a core with mixed uranium-plutonium fuel, and a boron carbide layer was added between the reactor vessel and reflector blocks. A computational study was conducted to justify the possibility of using relevant design solutions in a new reactor facility. Directions for further research were determined.
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nuclear fuel pulse periodic nuclear reactor fast-neutron reactor neptunium nitride MOX MNUP effectiveness of different fuel composition
Link for citing the article: Chereshkov D.G. Analysis of the Effectiveness of Fuel Composition Changing in a Pulse Fast-Neutron Research Reactor. Izvestiya vuzov. Yadernaya Energetika. 2026, no. 1, pp. 160-168; DOI: https://doi.org/10.26583/npe.2026.1.13 (in Russian).
