Development and Testing of a Methodology for Assessing of the Correlation Velocity Measurements’ Accuracy for the Hydrodynamic Investigations of the Turbulent Coolant Flow in Nuclear Reactor Elements

The correlation method of the coolant flow measuring is widely used in research practice including for studying of turbulent coolant flows in scale models of elements of nuclear power plants. The aim of this work was to develop a technique for assessing the effect of noise recorded by a measuring sy...

Full description

Saved in:
Bibliographic Details
Main Authors: I. A. Konovalov, A. A. Chesnokov, A. A. Barinov, S. M. Dmitriev, A. E. Khrobostov, M. A. Legchanov, S. S. Borodin, M. A. Makarov
Format: Article
Language:English
Published: Belarusian National Technical University 2021-03-01
Series:Приборы и методы измерений
Subjects:
Online Access:https://pimi.bntu.by/jour/article/view/701
Tags: Add Tag
No Tags, Be the first to tag this record!
_version_ 1849241605231345664
author I. A. Konovalov
A. A. Chesnokov
A. A. Barinov
S. M. Dmitriev
A. E. Khrobostov
M. A. Legchanov
S. S. Borodin
M. A. Makarov
author_facet I. A. Konovalov
A. A. Chesnokov
A. A. Barinov
S. M. Dmitriev
A. E. Khrobostov
M. A. Legchanov
S. S. Borodin
M. A. Makarov
author_sort I. A. Konovalov
collection DOAJ
description The correlation method of the coolant flow measuring is widely used in research practice including for studying of turbulent coolant flows in scale models of elements of nuclear power plants. The aim of this work was to develop a technique for assessing the effect of noise recorded by a measuring system on the flow rate readings obtained using the correlation method.A technique to assess the effect of noise as well as the relative position and acquisition period of sensors is presented. An insignificant concentration of a salt solution (NaCl or Na2SO4 ) is used as a passive impurity which creates a conductivity gradient of the medium recorded by a conductometric system. Turbulent pulsations at the interface between two concurrent isokinetic flows in a channel with a square cross section are used as the signal source for the correlational algorithm.Paper presents the values of  the  turbulence′s  transport  time  between  spatial  conductometers, the results of estimating the spectral power density and band of the recorded signal and also the signalto-noise ratios of the measuring system obtained on their basis which are subsequently used to estimate the confidence interval of the transport time.As a result of measurements the relationship between the confidence  interval  value  and  the signal length were obtained. The measurements which were carried out at different relative positions of conductometers make it  possible  to  make  a  conclusion  about  an  increase  in  the  spectral  width of the signal and, as a consequence, a decrease in the length of the confidence interval with increasing of distance between sensors.The presented work is an approbation of this approach for its application as part of an experimental model of a nuclear reactor in order to determine per-channel flow rates in the channels of the core simulator using mesh conductometric sensors taking into account the effect of noise.
format Article
id doaj-art-fd2fcdaf2ca8455da4ecf9423dcbb83d
institution Kabale University
issn 2220-9506
2414-0473
language English
publishDate 2021-03-01
publisher Belarusian National Technical University
record_format Article
series Приборы и методы измерений
spelling doaj-art-fd2fcdaf2ca8455da4ecf9423dcbb83d2025-08-20T04:00:07ZengBelarusian National Technical UniversityПриборы и методы измерений2220-95062414-04732021-03-01121677410.21122/2220-9506-2021-12-1-67-74538Development and Testing of a Methodology for Assessing of the Correlation Velocity Measurements’ Accuracy for the Hydrodynamic Investigations of the Turbulent Coolant Flow in Nuclear Reactor ElementsI. A. Konovalov0A. A. Chesnokov1A. A. Barinov2S. M. Dmitriev3A. E. Khrobostov4M. A. Legchanov5S. S. Borodin6M. A. Makarov7Nizhny Novgorod State Technical Univercity n.a. R.E. AlekseevNizhny Novgorod State Technical Univercity n.a. R.E. AlekseevNizhny Novgorod State Technical Univercity n.a. R.E. AlekseevNizhny Novgorod State Technical Univercity n.a. R.E. AlekseevNizhny Novgorod State Technical Univercity n.a. R.E. AlekseevNizhny Novgorod State Technical Univercity n.a. R.E. AlekseevNizhny Novgorod State Technical Univercity n.a. R.E. AlekseevNizhny Novgorod State Technical Univercity n.a. R.E. AlekseevThe correlation method of the coolant flow measuring is widely used in research practice including for studying of turbulent coolant flows in scale models of elements of nuclear power plants. The aim of this work was to develop a technique for assessing the effect of noise recorded by a measuring system on the flow rate readings obtained using the correlation method.A technique to assess the effect of noise as well as the relative position and acquisition period of sensors is presented. An insignificant concentration of a salt solution (NaCl or Na2SO4 ) is used as a passive impurity which creates a conductivity gradient of the medium recorded by a conductometric system. Turbulent pulsations at the interface between two concurrent isokinetic flows in a channel with a square cross section are used as the signal source for the correlational algorithm.Paper presents the values of  the  turbulence′s  transport  time  between  spatial  conductometers, the results of estimating the spectral power density and band of the recorded signal and also the signalto-noise ratios of the measuring system obtained on their basis which are subsequently used to estimate the confidence interval of the transport time.As a result of measurements the relationship between the confidence  interval  value  and  the signal length were obtained. The measurements which were carried out at different relative positions of conductometers make it  possible  to  make  a  conclusion  about  an  increase  in  the  spectral  width of the signal and, as a consequence, a decrease in the length of the confidence interval with increasing of distance between sensors.The presented work is an approbation of this approach for its application as part of an experimental model of a nuclear reactor in order to determine per-channel flow rates in the channels of the core simulator using mesh conductometric sensors taking into account the effect of noise.https://pimi.bntu.by/jour/article/view/701spatial conductometrywire mesh sensormodeling of processes in the elements of nuclear power units
spellingShingle I. A. Konovalov
A. A. Chesnokov
A. A. Barinov
S. M. Dmitriev
A. E. Khrobostov
M. A. Legchanov
S. S. Borodin
M. A. Makarov
Development and Testing of a Methodology for Assessing of the Correlation Velocity Measurements’ Accuracy for the Hydrodynamic Investigations of the Turbulent Coolant Flow in Nuclear Reactor Elements
Приборы и методы измерений
spatial conductometry
wire mesh sensor
modeling of processes in the elements of nuclear power units
title Development and Testing of a Methodology for Assessing of the Correlation Velocity Measurements’ Accuracy for the Hydrodynamic Investigations of the Turbulent Coolant Flow in Nuclear Reactor Elements
title_full Development and Testing of a Methodology for Assessing of the Correlation Velocity Measurements’ Accuracy for the Hydrodynamic Investigations of the Turbulent Coolant Flow in Nuclear Reactor Elements
title_fullStr Development and Testing of a Methodology for Assessing of the Correlation Velocity Measurements’ Accuracy for the Hydrodynamic Investigations of the Turbulent Coolant Flow in Nuclear Reactor Elements
title_full_unstemmed Development and Testing of a Methodology for Assessing of the Correlation Velocity Measurements’ Accuracy for the Hydrodynamic Investigations of the Turbulent Coolant Flow in Nuclear Reactor Elements
title_short Development and Testing of a Methodology for Assessing of the Correlation Velocity Measurements’ Accuracy for the Hydrodynamic Investigations of the Turbulent Coolant Flow in Nuclear Reactor Elements
title_sort development and testing of a methodology for assessing of the correlation velocity measurements accuracy for the hydrodynamic investigations of the turbulent coolant flow in nuclear reactor elements
topic spatial conductometry
wire mesh sensor
modeling of processes in the elements of nuclear power units
url https://pimi.bntu.by/jour/article/view/701
work_keys_str_mv AT iakonovalov developmentandtestingofamethodologyforassessingofthecorrelationvelocitymeasurementsaccuracyforthehydrodynamicinvestigationsoftheturbulentcoolantflowinnuclearreactorelements
AT aachesnokov developmentandtestingofamethodologyforassessingofthecorrelationvelocitymeasurementsaccuracyforthehydrodynamicinvestigationsoftheturbulentcoolantflowinnuclearreactorelements
AT aabarinov developmentandtestingofamethodologyforassessingofthecorrelationvelocitymeasurementsaccuracyforthehydrodynamicinvestigationsoftheturbulentcoolantflowinnuclearreactorelements
AT smdmitriev developmentandtestingofamethodologyforassessingofthecorrelationvelocitymeasurementsaccuracyforthehydrodynamicinvestigationsoftheturbulentcoolantflowinnuclearreactorelements
AT aekhrobostov developmentandtestingofamethodologyforassessingofthecorrelationvelocitymeasurementsaccuracyforthehydrodynamicinvestigationsoftheturbulentcoolantflowinnuclearreactorelements
AT malegchanov developmentandtestingofamethodologyforassessingofthecorrelationvelocitymeasurementsaccuracyforthehydrodynamicinvestigationsoftheturbulentcoolantflowinnuclearreactorelements
AT ssborodin developmentandtestingofamethodologyforassessingofthecorrelationvelocitymeasurementsaccuracyforthehydrodynamicinvestigationsoftheturbulentcoolantflowinnuclearreactorelements
AT mamakarov developmentandtestingofamethodologyforassessingofthecorrelationvelocitymeasurementsaccuracyforthehydrodynamicinvestigationsoftheturbulentcoolantflowinnuclearreactorelements