Combined numerical and experimental investigations of local hydrodynamics and coolant flow mass transfer in Kvadrat-type fuel assemblies of PWR reactors with mixing grids

Dmitriev, S. M.; Samoilov, O. B.; Khrobostov, A. E.; Varentsov, A. V.; Dobrov, A. A.; Doronkov, D. V.; Sorokin, V. D.

doi:10.1134/s0040601514080059

Cited by 12 publications

(2 citation statements)

References 1 publication

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“…Для изучения особенностей течения потока теплоносителя в Институте ядерной энергетики и технической физики Нижегородского государственного технического университета имени Р. Е. Алексеева функционирует аэродинамический экспериментальный стенд, представляющий собой разомкнутый контур, через который прокачивается воздух. В состав стенда входят: вентилятор высокого давления, ресиверная емкость, экспериментальная модель (ЭМ), расходомерное устройство, измерительный комплекс [3].…”

Section: экспериментальный стендunclassified

Regularities of Formation of Flow of Coolant Behind the TVS-Kvadrat Mixing Spacing Grid of the PWR-Type Reactor

Dmitriev¹,

Doronkov²,

Legchanov³

et al. 2018

Izv. vysh. ucheb

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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.

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Section: экспериментальный стендunclassified

Regularities of Formation of Flow of Coolant Behind the TVS-Kvadrat Mixing Spacing Grid of the PWR-Type Reactor

Dmitriev¹,

Doronkov²,

Legchanov³

et al. 2018

Izv. vysh. ucheb

Self Cite

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“…The most accurate method of obtaining these data can be an aerodynamic experiment using an enlarged model of the fuel assembly [12][13][14][15]. However, taking into account the active use of CFD programs for thermal-hydraulic calculations in nuclear industry [16][17][18][19][20], the authors of this work carried out a numerical simulation of the coolant flow in the fragment of a fuel assembly using Ansys CFX.…”

Section: Introductionmentioning

confidence: 99%

Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly

et al. 2018

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An innovative core with an increased energy resource was used when designing RITM-200 reactor unit. The paper presents the results of experimental and numerical simulation of hydrodynamic processes occurring in the inlet region of the RITM reactor fuel assembly model. Computational mesh of fuel assembly, containing ~ 22 million elements was created using Ansys ICEM CFD. The values of relative axial velocities in several cross sections at the inlet to the bundle of fuel elements are obtained. At the inlet to the fuel rods bundle the velocity field is not uniform, due to the complex geometry of the fuel assembly. The obtained results of CFD-simulation can be used to determine the input boundary conditions for subchannel programs of the core thermal-hydraulic analysis. This allows taking into account uneven flow rate distribution in subchannels due to the complex geometry of the fuel assembly inlet region.

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Hydrodynamics of coolant in VVER reactor core with fuel assemblies of various designs

Dmitriev

Герасимов

Dobrov

et al. 2020

J. Phys.: Conf. Ser.

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The article presents the results from experimental investigations into local coolant flow fluid dynamics that were carried out on the fragmental model of a VVER-type pressurized water reactor’s mixed core consisting of two types of fuel assemblies (FAs): TVSA-T (one segment) and TVSA-T.mod.2 (two segments). The coolant flow processes in the fuel rod bundle were simulated on an aerodynamic test bench. The pressure field in the flow was measured using a five-channel pneumometric probe. The obtained pressure field in the flow was recalculated for the coolant velocity vector according to the dependences derived during calibration. For drawing up a detailed flow motion pattern, a characteristic model cross section area was separated, which included the space between the assemblies and four fuel rod rows in each TVSA-type fuel assembly. The spatial distribution of coolant flow velocity projections was analyzed, as a result of which it became possible to reveal the regularities associated with the streamlining of spacer, mixing-, and combined-spacer grids in TVSA assemblies by coolant; to determine coolant cross flows resulting from streamlining of hydraulically nonidentical grids and to determine their localization in the experimental model longitudinal and cross sections; and to reveal the effect of accumulating flow hydrodynamic disturbances in the model longitudinal and cross sections resulting from the staggered arrangement of hydraulically nonidentical grids. The results obtained from investigations of interassembly interaction of coolant between the neighboring TVSA-T and TVSA-T.mod.2 assemblies have been adopted for practical use at JSC “Afrikantov OKBM” in estimating the thermal reliability of VVER-type reactor cores and have been included in the database for verification of computation fluid dynamics computer programs (CFD codes) and detailed cell-wise numerical analysis of VVER reactors’ core.

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Combined numerical and experimental investigations of local hydrodynamics and coolant flow mass transfer in Kvadrat-type fuel assemblies of PWR reactors with mixing grids

Cited by 12 publications

References 1 publication

Regularities of Formation of Flow of Coolant Behind the TVS-Kvadrat Mixing Spacing Grid of the PWR-Type Reactor

Regularities of Formation of Flow of Coolant Behind the TVS-Kvadrat Mixing Spacing Grid of the PWR-Type Reactor

Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly

Hydrodynamics of coolant in VVER reactor core with fuel assemblies of various designs

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