Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

DOI: 10.55176/2414-1038-2020-2-15-21

Authors & Affiliations

Klinov D.A., Gulevich A.V., Eliseev V.A., Usanov V.I., Dekusar B.M., Tormyshev I.V., Buriyevskiy I.V., Dolgikh V.P., Mishin V.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Klinov D.A. – First Deputy Director General for Science, PhD (Tech.).
Gulevich A.V. – Deputy Director of Nuclear Energetic Department, Dr. Sci. (Tech.).
Eliseev V.A. – Leading Researcher of Nuclear Energetic Department, PhD (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-84-47, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.
Usanov V.I. – Principal scientist, Dr. Sci. (Tehn.).
Dekusar B.M. – Leading Researcher, Cand. Sci. (Tehn.).
Tormyshev I.V. – Leading Engineer.
Buryevsky I.V. – Senior Researcher of Nuclear Energetic Department.
Dolgikh V.P. – Senior Researcher, Cand. Sci. (Tehn.).
Mishin V.A. – Junior Researcher.


The concept of the development of two-component nuclear energy based on fast and thermal reactors, adopted in Russia, suggests that in case of intensive development of nuclear reactors, fast reactors will provide fuel for thermal neutron reactors, while plutonium from VVER SNF will be used to produce mixed uranium-plutonium (MOX) fuel fast sodium reactors.
Currently, in the global nuclear energy sector, some PWR units are licensed to use a combination of conventional and MOX fuel in them or are in the process of licensing. But plutonium obtained during the reprocessing of spent fuel from the MOX fuel cannot be reused in thermal reactors due to an exceedingly high content of heavy (even) isotopes that do not fission in the thermal-neutron spectrum. As a result, plutonium is accumulated, which is a definite problem for European energy.
This problem can be partially solved with the help of fast reactors. Currently, fast energy sodium reactors operate only in Russia – BN-600 and BN-800. BN-800 can operate on MOX fuel, industrial remote technologies to fabricate such fuel is now being developed at a plant belonging to the Mining and Chemical Complex. Having a fast reactor and remote MOX fuel technologies, it becomes possible to organize the export of services – ″improve″ of foreign-grade plutonium unsuitable for reuse in thermal reactors.
The joint use of Russian fast reactor technologies and French MOX fuel technologies in thermal reactors for Russia opens up the world export market for plutonium enrichment services, and for the whole world – a new stage in the development of global two-component nuclear energy.

two-component nuclear energy, fast neutron reactor, thermal reactor, MOX fuel, change of plutonium isotopic composition ("improvement")

Article Text (PDF, in Russian)


UDC 621.039.51

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2020, issue 2, 1:2