EDN: JOCIDU
Authors & Affiliations
Pastukhova P.V., Zarapina E.M., Mishin V.A., Peregudov A.A., Yakovleva V.V.
A.I. Leipunsky Institute of 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, 80-56); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Zarapina E.M. – Junior Researcher.
Mishin V.A. – Junior Researcher.
Peregudov A.A. – Head of Department of Calculated Research of NPP Safety.
Yakovleva V.V. – Research Engineer.
Abstract
Computational research in the field of fast reactors is based on the use of diffusion and precision codes. Over the years of use, software complexes – scientific support codes have shown their high efficiency.
Fast neutron reactors are currently being actively developed and used to conduct reactor experiments to develop new types of fuels and structural materials. In this regard, the task of operational support of fast reactors with reliable calculated predictions of high accuracy is reaching a new level. To do this, the new-generation BNcode computing complex needs to be adapted for scientific support of not only the BN-800 reactor, but also the BN-600, and in the future the BN-1200M.
The objective of this work is to verify the BNcode computing complex for support of the BN-600 reactor.
Calculations were performed for several micro-companies, for which detailed and simplified models were created.
The contribution assessed the advantages and benefits of the BN-600 reactor design support software at IPPE JSC, namely the ModExSys system and the BNcode complex, which ensure reliable, safe operation of power units, modeling of irradiation conditions and measurements with a high level of functionality and productivity.
The article presents the results of calculations obtained according to the engineering program and precision code for the following values: criticality, maximum reactivity margin, efficiency of control systems, subcritical level, changes in the isotopic composition of materials when calculating burnout. The calculations were performed using the MMKKENO and TRIGEX programs (using the CROSSER/BNAB-93/ROSFOND2010 and 2020.2 constant preparation system).
Keywords
calculation methodology, two-component NPS, closure of the NFC, fast neutron reactor, computational maintenance of operation, automated calculation complex, BN-600, BN-800, criticality, efficiency of control systems, subcritical level, MMKKENO, TRIGEX
Article Text (PDF, in Russian)
References
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UDC 539.1
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 4, 4:7
