The study of hydrodynamic processes of a coolant flow in FA-KVADRAT PWR with various mixing spacer grids

Dmitriev, S. M.; Dobrov, A. A.; Doronkov, D. V.; Pronin, A. N.; Solntsev, D. N.; Sorokin, V. D.; Khrobostov, A. E.

doi:10.1134/s0869864318050062

Cited by 8 publications

(2 citation statements)

References 4 publications

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“…The coolant flow in the core was modeled using a wind tunnel test facility (Gerasimov et al 2020, Samoylov et al 2019, Dmitriyev et al 2014a, 2018, Varentsov et al 2012.…”

Section: Test Facilitymentioning

confidence: 99%

Experimental investigation of the coolant flow in the VVER reactor core with TVSA fuel assemblies

Dmitriyev¹,

Герасимов²,

Dobrov³

et al. 2021

NUCET

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The paper presents the results of an experimental study to investigate the coolant interaction in adjoining fuel assemblies in the VVER reactor core composed of TVSA-T and upgraded TVSA FAs. The processes of the in-core coolant flow were simulated in a test wind tunnel. The experiments were conducted using models representing different portions of the VVER reactor core fuel bundle and consisted in measuring the radial and axial airflow velocities in representative areas within the FAs and in the interassembly space. The results of the experiments can be translated to the full-scale conditions of the coolant flow with the use of the fluid dynamics simulation theory. The measurements were performed using a five-channel pressure-tube probe. The coolant flow pattern in different portions of the fuel bundle is represented by distribution diagrams and distribution maps for the radial and axial velocity vector components in the representative areas of the models. An analysis for the spatial distribution of the radial and axial velocity vector components has made it possible to obtain a detailed pattern of the coolant flow about the FA spacer, mixing and combined spacer grids of different designs. The accumulated database for the coolant flow in FAs of different designs forms the basis for the engineering justification of the VVER reactor core reliability and serviceability. The investigation results for the coolant interaction in adjoining TVSA FAs of different designs have been adopted for the practical use at JSC Afrikantov OKBM to estimate the heat-engineering reliability of the VVER reactor cores and have been included in the database for verification of computational fluid dynamics (CFD) codes and detailed by-channel calculation codes.

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“…The coolant flow in the core was modeled using a wind tunnel test facility (Gerasimov et al 2020, Samoylov et al 2019, Dmitriyev et al 2014a, 2018, Varentsov et al 2012.…”

Section: Test Facilitymentioning

confidence: 99%

Experimental investigation of the coolant flow in the VVER reactor core with TVSA fuel assemblies

Dmitriyev¹,

Герасимов²,

Dobrov³

et al. 2021

NUCET

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“…Моделирование течения теплоносителя в активной зоне производилось на аэродинамическом стенде в лаборатории «Реакторная гидродинамика» НГТУ имени Р. Е. Алексеева [3][4][5][6].…”

Section: экспериментальный стендunclassified

Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor

et al. 2020

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The article presents the results of experimental studies of the local hydrodynamics of the coolant flow in the mixed core of the VVER reactor, consisting of the TVSA-T and TVSA-T mod.2 fuel assemblies. Modeling of the flow of the coolant flow in the fuel rod bundle was carried out on an aerodynamic test stand. The research was carried out on a model of a fragment of a mixed core of a VVER reactor consisting of one TVSA-T segment and two segments of the TVSA-T.mod2. The flow pressure fields were measured with a five-channel pneumometric probe. The flow pressure field was converted to the direction and value of the coolant velocity vector according to the dependencies obtained during calibration. To obtain a detailed data of the flow, a characteristic cross-section area of the model was selected, including the space cross flow between fuel assemblies and four rows of fuel rods of each of the TVSA fuel assemblies. In the framework of this study the analysis of the spatial distribution of the projections of the velocity of the coolant flow was fulfilled that has made it possible to pinpoint regularities that are intrinsic to the coolant flowing around spacing, mixing and combined spacing grates of the TVSA. Also, the values of the transverse flow of the coolant caused by the flow along hydraulically nonidentical grates were determined and their localization in the longitudinal and cross sections of the experimental model was revealed. Besides, the effect of accumulation of hydrodynamic flow disturbances in the longitudinal and cross sections of the model caused by the staggered arrangement of hydraulically non-identical grates was determined. The results of the study of the coolant cross flow between fuel assemblies interaction, i.e. between the adjacent TVSA-T and TVSA-T mod.2 fuel assemblies were adopted for practical use in the JSC of “Afrikantov OKB Mechanical Engineering” for assessing the heat engineering reliability of VVER reactor cores; also, they were included in the database for verification of computational hydrodynamics programs (CFD codes) and for detailed cell-based calculation of the reactor core.

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Experimental study of local void fraction distribution in bubble flow in rod assembly

Vorobyev

Kashinsky

2019

J. Phys.: Conf. Ser.

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In this work an experimental study of local void fraction distribution in square arrangement rod bundle channel 3 * 3 under bubble flow regime was carried out. Measurements were performed with conductivity probe help, which was introduced into the flow through an angular or side rod at an angle of 15° to the flow. This method made it possible to determine the local void fraction close to the walls of the rods and in the narrow gap between them. Measurements have shown that a dome-shaped profile of local void fraction is realized in the gap between the side rode and the central one, while a saddle-shaped distribution of the void fraction is observed on the line connecting the central and angular rods. Also the effect of the spacer grid on the distribution of the gas phase in the channel was shown.

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The study of hydrodynamic processes of a coolant flow in FA-KVADRAT PWR with various mixing spacer grids

Cited by 8 publications

References 4 publications

Experimental investigation of the coolant flow in the VVER reactor core with TVSA fuel assemblies

Experimental investigation of the coolant flow in the VVER reactor core with TVSA fuel assemblies

Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor

Experimental study of local void fraction distribution in bubble flow in rod assembly

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