Authors & Affiliations
Semenov M.Y.1, Mikhailov G.M.1,
Peregudov A.A.1, Mishin V.A.1, Dyachenko Y.V.1,
Belov S.B.2, Kuznetsov A.E.2, Zheltyshev V.A.3,
Lyapin E.P.3, Dubovoy G.Y.3
1 A.I.
Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 Afrikantov Experimental Design Bureau for
Mechanical Engineering, Nizhny Novgorod, Russia
3 Branch of
Rosenergoatom Concern Joint Stock Company “Beloyarsk Nuclear Power Plant”,
Zarechnyj, Russia
Semenov M.Yu.1 – Leading Researcher, Cand. Sci. (Phys. and Math.).
Mikhailov G.M.1 – Head of the Laboratory Cand. Sci. (Tech.).
Peregudov A.A.1 – Deputy Director of the NEA for Innovative Development, Cand. Sci. (Tech.).
Mishin V.A.1 – Junior Researcher. Contacts: 1, Sq. Bondarenko, Obninsk, Kaluga Region, 249033. Tel.: +7 (484) 399–85–65; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Dyachenko Ya.V.1 – Research Engineer of the 1st Category.
Kuznetsov A.E.2 – Leading Research Engineer.
Belov S.B.2 – Head of the Calculation Bureau of the BN Reactor Core Development Department.
Zheltyshev V.A.3 – Head of the Group.
Lyapin E.P.3 – Head of JFL.
Dubovoy G.Yu.3 – Physics Engineer of the 1st Category.
Abstract
From 2016 to the present day, the BN-800
reactor with a hybrid core is being commercially operated in Russia. During
this time, a large amount of experimental data on basic neutron-physical
characteristics of the core has been collected. The loading of the hybrid core
was permanently changed during the initial time period: different ratio of fuel
assemblies with uranium fuel and MOX fuel and also the number of fuel
assemblies of medium- and highly-enriched zones. In 2021 the transition to a
full core loading with MOX fuel began, which is planned to be completed in
2022. In order to confirm the reasonability of the calculated prediction of
neutron-physical characteristics of the BN-800 core, work has been performed to
analyze the methods of computational support for the operation of the reactor
and to compare the calculated values of the neutron-physical characteristics
with the available experimental data.
The calculations
were performed using the MMKC code, which implements the Monte-Carlo method, as
well as JARFR and GEFEST800 in the diffusion approximation. The comparison of
the calculation results for all codes with measurement results allowed to
estimate the methodological error in the calculation of the basic neutron-physical
characteristics.
Calculations were
performed for the first five micro-campaigns of BN-800.
The analysis of
the following neutron-physical characteristics was performed:
– The value of the reactivity margin at the beginning and the end of the
campaign.
– Values of
subcriticality levels during reload and after SR withdrawal.
– Efficiency of
single CPS rods and CPS groups.
– Temperature-power effect of reactivity.
Keywords
BN reactor, BN-800, support code, precision neutron-physical code, Monte-Carlo method, MOX fuel, hybrid core
Article Text (PDF, in Russian)
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