DOI: 10.55176/2414-1038-2019-3-120-127
Authors & Affiliations
Chudinova V.A., Nikonov S.P.
National Research Nuclear University “MEPhI”, Moscow, Russia
Chudinova V.A. – postgraduate student, National Research Nuclear University “MEPhI”. Contacts: 31, Kashirskoe shosse, Moscow, Russia, 115409. Tel.: +7(925)574-68-44; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Nikonov S.P. – Senior Scientist, Associate Professor, Cand. Sci. (Techn.), National Research Nuclear University “MEPhI”.
Abstract
This paper presents the results of calculations on the heat-hydraulic model of a reactor with lead coolant, which is based on the design scheme for the ATHLET code, obtained on the basis of public information on the BREST-OD-300. In the model used in this work, firstly, the descending sections of each loop are interconnected by transverse hydraulic connections and, secondly, the in-reactor space from the lower pressure collector of the reactor to the upper distributing collector of the reactor is also divided into a system of parallel cross-linked channels. The model includes a reactor, four circuits with main circulation pumps, two sectional steam generators on each loop. The secondary loop for each steam generator has a feed pump. The article describes the method of obtaining the initial stationary state for the developed scheme and presents the results of the calculation of the transitional regime associated with the disconnection of one of the MCP with saving the reactor power. It is shown that in the emergency loop a reverse coolant current occurs when the MCP is disconnected. This leads to the fact that less coolant flow passes through the core.The cold coolant from the fourth loop is not fed to the entrance to the core, but is mixed in the upper distributing collector after the core.
Keywords
reactor facility, lead, metal coolant, design model, nuclear power plant, ATHLET, thermal hydraulic calculations, transient processes, modeling
Article Text (PDF, in Russian)
References
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UDC 621.039
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 3, 3:11
