EDN: GIIRFJ
Authors & Affiliations
Pastukhova P.V., Mishin V.A., Peregudov A.A., Semenov M.Yu., Dyachenko Ya.V., Zuikov A.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Pastukhova P.V. – Research Engineer. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-70-00 (add. 50-53); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Dyachenko Ya.V. – Research Engineer 1st Category.
Zuikov A.A. – Junior Researcher.
Mishin V.A. – Researcher.
Peregudov A.A. – Head of Department of Calculated Research of NPP Safety, Cand. Sci. (Tech.).
Semenov M.Yu. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Abstract
The current strategic direction is to continue the development of a two-component NES based on thermal and fast reactors in a closed nuclear fuel cycle to increase the competitiveness of nuclear energy in Russia. A significant stage in the implementation of the CNFC is the operation of the reactor
BN-800 core with a full load of MOX fuel.
The article provides information on the operation of the Beloyarsk NPP power unit № 4 from commissioning. The results of scientific and technical support for some of the main core indicators are presented and their changes related to such processes as: the start of reactor operation at capacity and subsequent extraction of PRC assemblies, a phased transition to full loading with MOX fuel and high-frequency plutonium, modernization of the modernization of the control roads system, transition to EK164-ID steel, fuel element testing with by including minor actinides to burn them out are analyzed.
The calculations were performed using the BNcode computing software package, which uses diffusion and transport approximations – the TRIGEX, MMKK and MMKС programs. The calculation results are shown on the corresponding diagrams and conclusions are made based on the values obtained.
This work demonstrates the importance of carrying out design maintenance of reactor installations, considering the accumulated experience and an informative base on the specifics of operating a fast reactor core for subsequent modernization to develop two-component nuclear power.
Thus, based on the available research data, it is possible to make conclusions about the operating parameters to determine the most accurate current and forecast design characteristics, substantiate safety, and fulfill regulations.
Keywords
two-component NPS, closure NFC, fast neutron reactor, design maintenance of operation, BN-800, MOX fuel, modernization of the control rods system, shell steel EK164-ID, minor actinides, reactor criticality, MRR, efficiency of the regulatory and protection system, subcritical level, proportion of delayed neutrons
Article Text (PDF, in Russian)
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UDC 621.039.58
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 1, 1:2
