REGULARITIES OF FORMATION OF FLOW OF COOLANT BEHIND THE TVS-KVADRAT MIXING SPACING GRID OF THE PWR-TYPE REACTOR
https://doi.org/10.21122/1029-7448-2019-61-3-258-268
Abstract
Tgratinghis paper presents the results of experimental investigations of the influence of mixing spacer gratings with different types of deflectors on the coolant flow in the TVSKvadrat fuel assembly of the PWR-type reactor. Experimental model of the TVS-Kvadrat of the PWR reactor was made in complete geometric similarity with the full-scale cassettes. Studies were carried out by modeling the flow of coolant in the core with the use of an experimental stand; the latter was an aerodynamic open loop through which air is pumped. To measure the local hydrodynamic characteristics of the coolant flow, special pneumatic sensors were used that were able to measure the full velocity vector at the point by its three components. During the studies of the local fluid dynamics of the coolant, the transverse flow rates were measured; also, the coolant flow rates were measured by cells of the TVS-Kvadrat experimental model. The analysis of the spatial distribution of the projections of the absolute flow velocity made it possible to detail the pattern of the coolant flow behind the mixing spacing gratings with different variants of the deflector design, as well as to choose the deflector of the optimal design. Accumulated data base on the flow of the coolant in the TVS-Kvadrat fuel assembly formed the basis of the engineering justification of the structures of the active zones of PWR reactors. Guidelines for choosing optimal designs mixing spacing grids have been considered by designers of the “Afrikantov OKBM” JSC when they created implementations of the latest TVS-Kvadrat assemblies. The results of experimental studies are used to verify CFD-codes of both foreign and domestic origin, as well as the programs for detailed cell-by-cell calculation of active zones in order to reduce conservatism in the justification of thermal reliability.
About the Authors
S. M. DmitrievRussian Federation
Address for correspondence: Dmitriev Sergei M. – Nizhny Novgorod State Technical University named after R. E. Alekseev, 24 Minin str., 603950, Nizhny Novgorod, Russian Federation. Tel.: +7 831 436-23-25 dmitriev@nntu.nnov.ru
D. V. Doronkov
Russian Federation
M. A. Legchanov
Russian Federation
V. D. Sorokin
Russian Federation
A. E. Khrobostov
Russian Federation
References
1. Dmitriev S. M., Zverev D. L., Bykh O. A., Panov Yu. K., Sorokin N. M., Farafonov V. A. (2013) Basic Equipment of NPP with Thermal Neutron Shell-Type Reactors. ?oscow, Mashinostroenie Publ. 413 (in Russian).
2. Barinov A. A., Dmitriev S. M., Khrobostov A. E., Samoilov O. B. (2016) Methods of Substantiation of Thermal Reliability of the Core of Thermal Water-Water Reactors. Atomic Energy, 120 (5), 335–341. https://doi.org/10.1007/s10512-016-0140-9.
3. Dmitriev S. M., Samoilov O. B., Khrobostov A. E., Varentsov A. V., Dobrov A. A., Doronkov D. V., Sorokin V. D. (2014) Ombined Numerical and Experimental Investigations of Local Hydrodynamics and Coolant Flow Mass Transfer in Kvadrat-Type Fuel Assemblies of PWR Reactors with Mixing Grids. Thermal Engineering, 61 (8), 558–565. https://doi.org/10.1134/s0040601514080059.
4. Borodin S. S., Dmitriev S. M., Legchanov M. A., Solntsev D. N., Sorokin V. D., Khrobostov A. E. (2014) Specific Features of Local Hydrodynamics and Mass Transfer of the Coolant in Fuel Assemblies of VVER and PWRS Reactorts with Mixing Gratings. Teplovye Protsessy v Tekhnike = Thermal Processes in Engineering, 5 (3), 98–107 (in Russian).
5. Dmitriev S. M., Borodin S. S. Legchanov M. A., Solntsev D. N., Sorokin V. D., Khrobostov A. E. (2013) Experimental Studies of Hydrodynamic and Mass-Transfer Properties of Coolant Flow in VVER Fuel Assemblies TVSA. Atomic Energy, 113 (5), 314–319. https://doi.org/10.1007/s10512-013-9638-6.
6. Borodin S. S., Varentsov A. V., Dobrov A. A., Dmitriev S. M., Pronin A. N., Solntsev D. N., Sorokin V. D., Khrobostov A. E. (2015) Numerical and Experimental Investigation of the Local Hydrodynamic and Mass Transfer Characteristics of the Flow of the Heat Carrier in the Alternative Fuel Assembly of VVER Reactors with Mixing Grids. Teplovye Protsessy v Tekhnike = Thermal Processes in Engineering, (4), 177–182 (in Russian).
7. Kashinskii O. N., Lobanov P. D., Pribaturin N. A., Kurdyumov A. S., Volkov S. E. (2013) Experimental Study of the Effect of Spacer grid on the Flow Structure in Fuel Assemblies of the AES 2006 Reactor. Thermal Engineering, 60 (1), 62–66. https://doi.org/10.1134/s0040601512070063.
8. Zhukov A. V., Sorokin A. P., Matyukhin N. M. (1989) Interchannel Exchange in Fuel Assemblies of Fast Reactors: a Theoretical Framework and Physics. Moscow, Energoatomizdat Publ. 183 (in Russian).
9. Gukhman A. A. (1973) Introduction to the Theory of Similarity. Moscow, Vysshaya Skola Publ. 295 (in Russian).
10. Mitrofanova O. V. (2010) Fluid Flow and Heat Transfer of Swirling Flows in Channels of Nuclear Power Plants. Moscow, Fizmatlit Publ. 288 (in Russian).
Review
For citations:
Dmitriev S.M., Doronkov D.V., Legchanov M.A., Sorokin V.D., Khrobostov A.E. REGULARITIES OF FORMATION OF FLOW OF COOLANT BEHIND THE TVS-KVADRAT MIXING SPACING GRID OF THE PWR-TYPE REACTOR. ENERGETIKA. Proceedings of CIS higher education institutions and power engineering associations. 2018;61(3):258-268. (In Russ.) https://doi.org/10.21122/1029-7448-2019-61-3-258-268