Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Saldikov I.S.1, Tikhomirov G.V.1, Ternovykh M.Yu.1, Khomyakov Y.S.2, Suslov I.R.2, Fomichenko P.A.3
1National Research Nuclear University “MEPhI”, Moscow, Russia
2ROSATOMS’s “Innovation and technology center for the “PRORYV” project” (ITCP), Moscow, Russia
3National Research Center "Kurchatov Institute", Moscow, Russia

Saldikov I.S. – Engineer, National Research Nuclear University “MEPhI”. Contacts: 31, Kashirskoen shosse, Moscow, Russia, 115409. Tel.: (495) 788-56-99; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Tikhomirov G.V. – Deputy Director of the Institute of Physics and Technology, Dr. Sci. (Phys. and Math.), Associate Professor, National Research Nuclear University “MEPhI”.
Ternovykh M.Yu. – Senior Lecturer, National Research Nuclear University “MEPhI”.
Khomyakov Yu.S. – Dr. Sci. (Phys. and Math.), ROSATOMS’s “Innovation and technology center for the “PRORYV” project” (ITCP).
Suslov I.R. – Chief Specialist, Cand. Sci. (Phys. and Math.), ROSATOMS’s “Innovation and technology center for the “PRORYV” project” (ITCP).
Fomichenko P.A. – Head of the laboratory of physical security, National Research Center "Kurchatov Institute".


The strategy of the development of nuclear power in Russia provides for use of fast power reactors in closed nuclear fuel cycle. The PRORYV (i.e. «Breakthrough» in Russian) project is currently under development. Within the framework of this project, fast reactors BN-1200 and BREST-OD-300 should be built to, inter alia, demonstrate possibility of the closed nuclear fuel cycle technologies with pluto-nium as a main source of energy. Russia has a large inventory of plutonium which was accumulated in the result of reprocessing of spent fuel of thermal power reactors and conversion of nuclear weapons. This kind of plutonium will be used for development of initial fuel assemblies for fast reactors. The closed nuclear fuel cycle concept of the PRORYV assumes self-supplied mode of operation with fuel regeneration by neutron capture reaction in non-enriched uranium, which is used as a raw material. Operating modes of reactors and its characteristics should be chosen so as to provide the self-sufficient mode by using of fissile isotopes while refueling by depleted uranium and to support this state during the entire period of reactor operation. Thus, the actual issue is modeling fuel handling processes. To solve these problems, the code REPRORYV (Recycle for PRORYV) has been developed. It simulates nuclide streams in non-reactor stages of the closed fuel cycle. At the same time various verified codes can be used to evaluate in-core characteristics of a reactor. By using this approach various options for nuclide streams and assess the impact of different plutonium content in the fuel, fuel processing conditions, losses during fuel processing, as well as the impact of initial uncertainties on neutron-physical characteristics of reactor are considered in this study. In this article the REPRORYV code is described in details.

closed nuclear fuel cycle, fast reactors, recycling, BN, BN-1200, BREST-OD-300

Article Text (PDF, in Russian)


UDC 621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2017, issue 1, 1:1