EDN: GMHNIU
Authors & Affiliations
Mitskevich A.V.1, Popov A.O.1, Volkova S.N.1, Gritsai A.S.1, 2
1 Alexandrov Research Institute of Technology, Sosnovy Bor, Russia
2 Peter the Great St. Petersburg Polytechnic University, Sosnovy Bor, Russia
Mitskevich A.V.1 – Engineer 2d Category.
Popov A.O.1 – Head of Group. Contacts: 72, Koporskoye shosse, Sosnovy Bor, Leningrad region, Russia, 188540. Tel.: +7 (81369) 60-366; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Volkova S.N.1 – Leading Researcher, Cand. Sci. (Tech.).
Gritsai A.S.1, 2 – Head of Department, Senior Lecturer, Department of NPP Design and Operation, Cand. Sci. (Tech.).
Abstract
A problem of current importance is the development of computer codes for safety analysis of nuclear reactors with liquid metal coolant.
In accordance with this, a specialized version of the KORSAR/LMR calculation code was developed that allows for numerical modelling of steady states, transient and emergency modes of LMC reactors.
The validity of numerical simulations greatly depends on the degree of elaboration of a system of closure relations for thermal-hydraulic models in computer codes.
The paper presents flow regime and heat transfer maps used in the KORSAR/LMR calculation code and serving as the basis for a closure relations system in this computer code. An analysis of the correlations for drag and heat transfer coefficients of the walls in channels with different geometries is presented. Closure relations for the two-phase region in the gas – liquid heavy metal coolant system are considered. Closure relations for interphase drag are chosen based on analysis of data in international literature. A modification of selected relations is proposed and the modified relations are validated against available experiment data.
The results of numerical modelling of experiments simulating inter-loop leakage are presented. The obtained results indicate the adequacy of the KORSAR/LMR computer code modeling of processes occurring in the LMC loops.
Keywords
closure relations, liquid metal coolant, computer code, two-phase flow, single-phase flow, interphase drag, interphase heat transfer, wall heat transfer, flow regime maps, heat transfer maps, liquid metal cooled reactors, KORSAR/LMR computer code
Article Text (PDF, in Russian)
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UDC 621.039:532.542:004.415
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 1, 1:13
