DOI: 10.55176/2414-1038-2019-2-77-86
Authors & Affiliations
Peregudov A.A.1, Kryachko M.V.1, Koscheev V.N.1, Maslov P.A.1, Tormyshev I.V.1, Semenov M.Yu.1, Cunzio G.A.1, Gurskaya O.S.1, Ivanov A.A.2, Erpalov P.A.2
1 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 Rosenergoatom Beloyarsk Nuclear Power Plant, Zarechnyj, Russia
Peregudov A.A. – Deputy Head of Laboratory, Cand Sci. (Techn.), A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7(484) 399-51-54; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Kryachko M.V. – Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
Koscheev V.N. – Leading Research, Cand. Sci. (Phys.-Math.), A.I. Leypunsky Institute for Physics and Power Engineering.
Maslov P.A. – Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
Tormyshev I.V. – Senior Research, A.I. Leypunsky Institute for Physics and Power Engineering.
Semenov M.Yu. – Leading Research, Cand. Sci. (Phys.-Math.), A.I. Leypunsky Institute for Physics and Power Engineering.
Cunzio G.A. – Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
Gurskaya O.S. – Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
Ivanov A.A. – Deputy Head of Department, Rosenergoatom Beloyarsk Nuclear Power Plant.
Erpalov P.A. – Engineer Physicist, Rosenergoatom Beloyarsk Nuclear Power Plant.
Abstract
The relevance of this work is due to the need of the supervisor (IPPE) to perform work on the control and maintenance of the operation of fast sodium reactors.
The purpose of this work is to develop an integrated code of a new generation for the scientific support of existing reactors BN-600 and BN-800 and in the future BN-1200.
The code being developed for scientific support of the fast reactor operation serves for current and predictive calculations of reactor characteristics, safety justification during overload, justification of the micro-campaign reactivity balance, compliance with established performance criteria for fuel elements and other elements. Also, this code will be used as an independent calculation tool of increased accuracy for confirming and, if necessary, correcting the results of the operational support received at the station, as well as for analyzing non-standard settlement situations of increased complexity, such as the justification for entering BN-600 and BN-800 irradiating devices for producing isotopes (in particular, 60Co), irradiation of fuel assemblies with a nitride type of fuel.
Keywords
BN, BN-600, BN-800, BN-1200 reactor, tracking code, precision neutron-physical code, Monte-Carlo method, isotope kinetics calculation module, thermal-hydraulic code of improved estimate, fuel archive
Article Text (PDF, in Russian)
References
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UDC 004.94:681.3.06
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 2, 2:8
