EDN: QSOSQN
Authors & Affiliations
Zalesov A.S.
OKB Gidropress, Podolsk, Russia
Zalesov A.S. – Lead Design Engineer. Contacts: 21, st. Ordzhonikidze, Podolsk, Moscow region, Russia, 142103. Tel.: +7 (495) 502-79-13, add. 15-86; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Abstract
The purpose of the presented work was to develop the MATADOR code for modeling heat and mass transfer processes in fuel assemblies of fast reactors with spacing by wire wrapped. In the article, the computational-theoretical models that take into account the influence of spiral wire winding within the framework of the sub-channel approach of the thermohydraulic calculation were analyzed. New correlations were implemented into the code to close the system of mass, momentum and energy transfer equations with a wide variation range of geometric and regime parameters. The efficiency of the changes made to the MATADOR code was confirmed by calculations based on the experiments performed at THEADES (Karlsruhe Liquid Metal Laboratory, Germany) and KYLIN-II (Institute of Nuclear Energy Safety Technology, China) test facilities with cooling of the rod bundles by lead-bismuth eutectic. The article provides a brief description of test bundles, calculation models and compares the results of calculations using the MATADOR code with experimental data and calculation results in the foreign sub-channel SACOS-PB code. Numerical simulation of hydrodynamics and heat transfer in rod bundles was carried out using generalized dependences for integral and local coefficients of inter-channel exchange. The analysis of computational studies confirmed the ability of the MATADOR code to reproduce experimental measurements with accuracy acceptable in engineering practice.
Keywords
subchannel (cell-by-cell) computer code, thermohydraulic calculation, heat transfer, hydrodynamics, liquid metal coolant, fast reactor, core, fuel assembly, fuel rod, wire wrapped
Article Text (PDF, in Russian)
References
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UDC 621.039.534…23
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 3, 3:15
