Abstract
The article presents the results of experimental studies of the influence of different designs of mixing spacer grids on the coolant flow in FA-KVADRAT PWR. The investigations were carried out by simulating the coolant flow in the core on the experimental air stand being an aerodynamic open loop through which air is pumped. To measure the local hydrodynamic characteristics of the coolant flow, special pneumometric sensors were used for measuring the total velocity vector and the flow rate value. During the investigations of the local hydrodynamics of the coolant, transverse flow velocity, as well as the coolant flow rates in the cells of the experimental model FA-KVADRAT, was measured. The analysis of spatial distribution of projections of absolute flow velocity allowed studying and detailing the coolant flow pattern behind the mixing spacer grids with different designs of deflectors as well as selecting the optimal design of the deflector. The accumulated database on the coolant flow in FA-KVADRAT has formed the basis for engineering assessment of active zones’ structures of PWR. The results of experimental studies are used to verify CFD codes (in both foreign and domestic development) as well as programs for detailed cell-by-cell calculation of active zones in order to reduce conservatism when assessing heat engineering reliability.
Similar content being viewed by others
References
S.M. Dmitriev, O.A. Byh, Yu.K. Panov, N.M. Sorokin, D.L Zverev, and V.A. Farafonov, The Main Equipment of Nuclear Power Plants with a Tank Reactor with Thermal Neutrons, Mashinostroenie, Moscow, 2013.
S.M. Dmitriev, A.A. Barinov, O.B. Samoilov, and A.E. Khrobostov, Methods of thermomechanical reliability validation of thermal water-moderated and water-cooled reactor cores, Atomic Energy, 2016, Vol. 120, No. 5, P. 335–341.
S.E. Volkov, O.N. Kashinskiy, A.S. Kurdyumov, P.D. Lobanov, and N.A. Pribaturin, Experimental study of effect of spacer grid on the flow structure in fuel assemblies of the AES 2006 Reactor, Thermal Engineering, 2013, Vol. 60, No.1, P. 62–66.
E.A. Lisenkov, S.M. Lobachev, Yu.A. Bezrukov, A.V. Seleznev, N.A. Pribaturin, V.G. Glavnyj, and S.E. Volkov, Coolant mixing investigation in VVER-1000 fuel assembly, Tyazheloe Mashinostroenie, 2012, No. 9, P. 5–13.
S.M. Dmitriev, A.V. Varentsov, A.A. Dobrov, D.V Doronkov, O.B. Samoilov, V.D. Sorokin, and A.E. Khrobostov, Combined numerical and experimental investigations of local hydrodynamics and coolant flow mass transfer in Kvadrat-type fuel assemblies of PWR reactors with mixing grids, Thermal Engng, 2014, No. 8, P. 558–565.
S.M. Dmitriev, S.S. Borodin, M.A. Legchanov, D.N. Solncev, V.D. Sorokin, and A.E. Hrobostov, Experimental studies of hydrodynamic and mass-transfer properties of coolant flow in VVER fuel assemblies TVSA, Atomic Energy, 2013, Vol. 113, No. 5, P. 314–319.
A.V. Zhukov, A.P. Sorokin, and N.M. Matyukhin, Interchannel Transfer in Fuel Assemblies of Fast Neutron Reactors: Theoretical Principles and Physics of the Process, Energoatomizdat, Moscow, 1989.
A. A. Gukhman, Introduction to Similarity Theory, Vysshaya Shkola, Moscow, 1973.
O.V. Mitrofanova, Hydrodynamics and Heat Transfer of Swirling Flows in Channels of Nuclear Power Plants, Fizmatlit, Moscow, 2010.
Author information
Authors and Affiliations
Corresponding author
Additional information
The work was carried out in the framework of the basic part of the public contract No. 13.8823.2017/8.9, and with the financial support of the grant of the President of the Russian Federation in the framework of the project MK- 2398.2018.8.
Rights and permissions
About this article
Cite this article
Dmitriev, S.M., Dobrov, A.A., Doronkov, D.V. et al. The study of hydrodynamic processes of a coolant flow in FA-KVADRAT PWR with various mixing spacer grids. Thermophys. Aeromech. 25, 695–703 (2018). https://doi.org/10.1134/S0869864318050062
Received:
Revised:
Published:
Issue Date:
DOI: https://doi.org/10.1134/S0869864318050062