EDN: AYWXEA
Authors & Affiliations
Klinov D.A.1, Semyonov M.Yu.1, Mikhailov G.M.1, Peregudov A.A.1, Mishin V.A.1, Izotov V.V.1, Kryukov A.N.2, Farakshin M.R.2, Belov S.B.2, Kiselev A.V.2, Kuznetsov A.E.2, Lyapin E.P.3
1 A.I. Leipunsky Institute of Physics and Power Engineering, Obninsk, Russia
2 Afrikantov Machine Building Experimental Design Bureau, Nizhny Novgorod, Russia
3 Branch of Rosenergoatom Concern Joint Stock Company “Beloyarsk Nuclear Power Plant”, Zarechny, Russia
Klinov D.A.1 – Deputy Scientific Supervisor for Advanced Topics, Cand. Sci. (Tech.).
Semenov M.Yu. 1 – Leading Researcher, Cand. Sci. (Phys.-Math.).
Mikhailov G.M.1 – Head of Laboratory, Cand. Sci. (Tech.).
Peregudov A.A.1 – Head of Department of Calculated Research of NPP Safety. Contact: 1, pl. Bondarenko, Obninsk, Kaluga Region, 249033. Tel: +7 (484) 399-51-54; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Mishin V.A.1 – Junior Researcher.
Izotov V.V.1 – Researcher.
Kryukov A.N.2 – Deputy Head of Department.
Farakshin M.R.2 – Head of BN Reactor Cores Development Department, Cand. Sci. (Tech.).
Belov S.B.2 – Head of the Bureau of Calculations, BN Reactor Core Development Department.
Kiselev A.V.2 – Design Engineer of BN Reactor Cores Development Department.
Kuznetsov A.E.2 – Leading Research Engineer, Afrikantov Experimental Machine Building Design Bureau.
Lyapin E.P. 3 – Head of NPL .
Abstract
The main way to determine the energy release in the core of a fast reactor, in which, with a high probability, there is no operational hardware control of the energy release distribution, is the computational modeling of the neutron field. The accuracy of these heat release calculations is a significant element in confirming the reliable operation of fuel elements and fuel assemblies. Also, knowledge of the heat release distribution calculation error is important for core design, in terms of assigning design limits and reserves that determine the technical and economic characteristics of the power unit. Operation of the BN-800 reactor allows numerical evaluation of the accuracy of design and operating codes under real conditions.
This paper presents information on the study of heat release distribution in the core of the BN-800 reactor using the method of gamma-scanning of fuel assemblies. The measurements were carried out for “fresh” MOX fuel assemblies pre-activated in the BN-800 reactor core before the start of the 11 microcampaign, which was the first microcampaign of the MOX fuel core.
The paper presents a comparison of calculated and experimental data. The calculations were performed using the programs JARFR, GEFEST800 and TRIGEX. For all programs, the unified CONSYST constant preparation system with the ABBN-93 group library was used.
Keywords
BN reactor, BN-800, gamma-scanning, energy release, Monte-Carlo method, MOX fuel, JARFR program, GEFEST800 program, TRIGEX program
Article Text (PDF, in Russian)
References
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UDC 621.039.519
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 1, 1:2
