Authors & Affiliations

Tsibulskiy S.V.
National Research Centre "Kurchatov Institute", Moscow, Russia

Tsibulskiy S.V. – Junior Researcher, National Research Centre "Kurchatov Institute". Contacts: 1, Akademika Kurchatova pl., Moscow, Russia, 123182. Tel:+7(499) 196-73-77; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..


There are separate of fissile isotopes in a fuel rod in the fuel load admit the transition to a closed fuel circle in the nuclear power industry. For this solution to consider the formation of heterogeneous fuel pellet in which the fissile and raw isotope are separate and not mixed together. The raw material iso-tope is located in the peripheral zone. Fissile isotope, placed in the center of fuel pin holds 10% of the volume. There is row isotope in the periphery.
All calculations for this research were made with UNK code. This code was complemented with a module, which allows calculating temperatures in pin cell. At present UNK allows solving of neutron-physical task of neutron transport, burn-up task (isotope composition evolution) and temperature calculation.
Initial loading is plutonium, separated from spent fuel of the same cell of previous company. Irra-diated plutonium of the central part is sent to either long term storage or final disposal.
Energy plutonium location extracted from spent fuel of VVER in the central part of fuel pellet (heterogeneous pellet) decreases plutonium loading approximately 20 % in condition of the same company duration in comparison with UOX fuel.
In case of heterogeneous location, there is depleted uranium in the periphery on the pellet. And after irradiation received plutonium isotope composition can be used repeatedly to form new loadings. This solution is qualitatively different from MOX case, which does not allow further using.

Rod, heterogeneous, homogeneous, cell, fuel, cycle, fuel, program, closed, burnout, plutonium, energy, SNF, MOX

Article Text (PDF, in Russian)


UDC 621.039.51

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 2, 2:6