Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

DOI: 10.55176/2414-1038-2019-4-79-86

Authors & Affiliations

Seleznev E.F.1, Belov A.A.1, Drobichev Yu.Yu.1, Ivanov A.A.2, Mitrofanov S.Yu.2, Kuzmin A.S.2
1 Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia
2 Beloyarskaya Nuclear Power Plant, Zarechny, Russia

Seleznev E.F. – Chief Researcher, Nuclear Safety Institute of the Russian Academy of Sciences. Contacts: 52, Bolshaya Tulskaya st., Moscow, Russia, 115191. Tel.: +7 (495) 955-23-11; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Belov A.A. – Researcher, Nuclear Safety Institute of the Russian Academy of Sciences.
Drobichev Yu.Yu. – Engineer, Nuclear Safety Institute of the Russian Academy of Sciences.
Ivanov A.A. – Deputy Head of the Department of Nuclear Safety and Reability, Beloyarskaya Nuclear Power Plant.
Mitrofanov S.Yu. – Chief specialist Reactor Control Group (RCG), Beloyarskaya Nuclear Power Plant.
Kuzmin A.S. – Physical Engineer 2k, Beloyarskaya Nuclear Power Plant.


The paper presents the simulation results of the BN-800 reactor being placed in a critical state upon completion of 5 microcampaign when detectors are placed inside the reactor building in the vicinity of discharge elevators with a demonstration of signal levels in off-threshold (based on 235U) and threshold (based on 238U) detectors. The calculated data are supplemented by experimental signals from non-threshold detectors located in the same region of the reactor.
The computational simulation of the reactor exit to the critical state was carried out using three algorithms: the method of point kinetics; by solving a non-uniform stationary equation with an external neutron source; by solving a non-stationary equation with a space-time dependence of the neutron flux density, taking into account the presence of an external neutron source in the reactor.
In addition to directly evaluating the calculated behavior of the reactor power in the simulated process, the features of the used solution algorithms are analyzed.

experiment, detector, ionization fission chamber, rod extraction, nonstationary process, measurement, computational simulation, algorithm, critical state

Article Text (PDF, in Russian)


UDC 621.039

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 4, 4:9