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

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...

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Main Authors: S. M. Dmitriev, A. V. Gerasimov, A. A. Dobrov, D. V. Doronkov, A. N. Pronin, A. V. Ryazanov, D. N. Solntsev, A. E. Khrobostov
Format: Article
Language:Russian
Published: Belarusian National Technical University 2020-03-01
Series:Известия высших учебных заведений и энергетических объединенний СНГ: Энергетика
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Online Access:https://energy.bntu.by/jour/article/view/1937
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author S. M. Dmitriev
A. V. Gerasimov
A. A. Dobrov
D. V. Doronkov
A. N. Pronin
A. V. Ryazanov
D. N. Solntsev
A. E. Khrobostov
author_facet S. M. Dmitriev
A. V. Gerasimov
A. A. Dobrov
D. V. Doronkov
A. N. Pronin
A. V. Ryazanov
D. N. Solntsev
A. E. Khrobostov
author_sort S. M. Dmitriev
collection DOAJ
description 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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institution Kabale University
issn 1029-7448
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language Russian
publishDate 2020-03-01
publisher Belarusian National Technical University
record_format Article
series Известия высших учебных заведений и энергетических объединенний СНГ: Энергетика
spelling doaj-art-ee143919c6c24ae7828537009eab734f2025-02-03T11:34:17ZrusBelarusian National Technical UniversityИзвестия высших учебных заведений и энергетических объединенний СНГ: Энергетика1029-74482414-03412020-03-0163215116210.21122/1029-7448-2020-63-2-151-1621710Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER ReactorS. M. Dmitriev0A. V. Gerasimov1A. A. Dobrov2D. V. Doronkov3A. N. Pronin4A. V. Ryazanov5D. N. Solntsev6A. E. Khrobostov7Nizhny Novgorod State Technical University named after R. E. AlekseevNizhny Novgorod State Technical University named after R. E. AlekseevNizhny Novgorod State Technical University named after R. E. AlekseevNizhny Novgorod State Technical University named after R. E. AlekseevNizhny Novgorod State Technical University named after R. E. AlekseevNizhny Novgorod State Technical University named after R. E. AlekseevNizhny Novgorod State Technical University named after R. E. AlekseevNizhny Novgorod State Technical University named after R. E. AlekseevThe 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.https://energy.bntu.by/jour/article/view/1937corefuel assemblyspacing and combined spacing gratescoolant hydrodynamicscoolant cross flow between fuel assemblies’ interaction
spellingShingle S. M. Dmitriev
A. V. Gerasimov
A. A. Dobrov
D. V. Doronkov
A. N. Pronin
A. V. Ryazanov
D. N. Solntsev
A. E. Khrobostov
Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor
Известия высших учебных заведений и энергетических объединенний СНГ: Энергетика
core
fuel assembly
spacing and combined spacing grates
coolant hydrodynamics
coolant cross flow between fuel assemblies’ interaction
title Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor
title_full Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor
title_fullStr Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor
title_full_unstemmed Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor
title_short Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor
title_sort investigation of coolant local hydrodynamics in the mixed core of the vver reactor
topic core
fuel assembly
spacing and combined spacing grates
coolant hydrodynamics
coolant cross flow between fuel assemblies’ interaction
url https://energy.bntu.by/jour/article/view/1937
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AT dvdoronkov investigationofcoolantlocalhydrodynamicsinthemixedcoreofthevverreactor
AT anpronin investigationofcoolantlocalhydrodynamicsinthemixedcoreofthevverreactor
AT avryazanov investigationofcoolantlocalhydrodynamicsinthemixedcoreofthevverreactor
AT dnsolntsev investigationofcoolantlocalhydrodynamicsinthemixedcoreofthevverreactor
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