Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Evaluation of Neutron Physical Characteristics of the Conceptual Fast Neutron Reactor Cooled by Carbon Dioxide

9/25/2023 2023 - #03 Physics and technology of nuclear reactors

Semishin V.V.

DOI: https://doi.org/10.26583/npe.2023.3.03

UDC: 621.039.51

As part of the study of the neutron-physical characteristics of the concept of a gas-cooled fast neutron nuclear reactor with reduced energy density of fuel in the core and reduced coolant pressure in the primary circuit, an assessment of the possibility of functioning and nuclear safety when using various types of fuel was carried out. The possibility of reuse in this reactor of manufactured nuclear fuel from thermal reactors of the VVER-1000 type, which form the basis of the reactor fleet of the Russian Federation, and the involvement of plutonium produced at thermal reactors in the fuel cycle of the fast neutron nuclear reactor under consideration, is shown. Studies of fuel campaigns were carried out for several types of fuel: fresh enriched uranium dioxide; REMIX fuel, enriched with uranium-235; dump uranium, enriched with a mixture of plutonium isotopes extracted from SNF reactors of the VVER type.


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neutron physics calculation Desna SAPPHIRE fast neutrons fuel reuse remix two-component nuclear power plutonium

Link for citing the article: Semishin V.V. Evaluation of Neutron Physical Characteristics of the Conceptual Fast Neutron Reactor Cooled by Carbon Dioxide. Izvestiya vuzov. Yadernaya Energetika. 2023, no. 3, pp. 31-44; DOI: https://doi.org/10.26583/npe.2023.3.03 (in Russian).