Application of the Correlation Velocity Measurements for Hydrodynamic Investigations of Turbulent Coolant Flow in Nuclear Reactor Elements

The method of correlation measurement of the coolant flow rate, widely used for operational diagnostics of nuclear power plants, can be extensively used in research practice. The aim of this work was to apply a correlation method based on the conductometric measurement system with wire-mesh sensors...

Full description

Saved in:
Bibliographic Details
Main Authors: I. A. Konovalov, A. E. Khrobostov, M. A. Legchanov, D. N. Solncev, A. A. Barinov, A. V. Ryazanov, A. A. Chesnokov, M. A. Makarov
Format: Article
Language:English
Published: Belarusian National Technical University 2020-09-01
Series:Приборы и методы измерений
Subjects:
Online Access:https://pimi.bntu.by/jour/article/view/663
Tags: Add Tag
No Tags, Be the first to tag this record!
_version_ 1832557411977658368
author I. A. Konovalov
A. E. Khrobostov
M. A. Legchanov
D. N. Solncev
A. A. Barinov
A. V. Ryazanov
A. A. Chesnokov
M. A. Makarov
author_facet I. A. Konovalov
A. E. Khrobostov
M. A. Legchanov
D. N. Solncev
A. A. Barinov
A. V. Ryazanov
A. A. Chesnokov
M. A. Makarov
author_sort I. A. Konovalov
collection DOAJ
description The method of correlation measurement of the coolant flow rate, widely used for operational diagnostics of nuclear power plants, can be extensively used in research practice. The aim of this work was to apply a correlation method based on the conductometric measurement system with wire-mesh sensors for measuring a coolant flow rate.Insignificant concentration of a salt solution (NaCl or Na2SO4 ) creates a gradient of the conductivity in the flow, which is used as a passive scalar measured by the system. Authors used turbulent pulsations at the interface of two concurrent flows with identical velocities in a square channel as a signal source for the correlation method. The paper presents the methodology of the tests, test facility description, signalto-noise ratio estimation, the results of digital signal processing and comparison of the measured velocities in the model with the flowrate‒averaged velocity determined by the use of flowmeters. The measured velocity values give acceptable agreement for the turbulent flow modes. It was shown that the measurement accuracy drops sharply for low-Reynolds flows.The obtained results were used for flowrate measurements in core-imitator channels of the nuclear reactor test model. The presented paper is an approbation of this approach for its application as part of an test model of a nuclear reactor in order to determine the each duct flow rates in the channels of the core simulator using wire mesh sensors.
format Article
id doaj-art-e8b62a34d420449cb8982695f33024b1
institution Kabale University
issn 2220-9506
2414-0473
language English
publishDate 2020-09-01
publisher Belarusian National Technical University
record_format Article
series Приборы и методы измерений
spelling doaj-art-e8b62a34d420449cb8982695f33024b12025-02-03T05:16:51ZengBelarusian National Technical UniversityПриборы и методы измерений2220-95062414-04732020-09-0111319620310.21122/2220-9506-2020-11-3-196-203518Application of the Correlation Velocity Measurements for Hydrodynamic Investigations of Turbulent Coolant Flow in Nuclear Reactor ElementsI. A. Konovalov0A. E. Khrobostov1M. A. Legchanov2D. N. Solncev3A. A. Barinov4A. V. Ryazanov5A. A. Chesnokov6M. 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 method of correlation measurement of the coolant flow rate, widely used for operational diagnostics of nuclear power plants, can be extensively used in research practice. The aim of this work was to apply a correlation method based on the conductometric measurement system with wire-mesh sensors for measuring a coolant flow rate.Insignificant concentration of a salt solution (NaCl or Na2SO4 ) creates a gradient of the conductivity in the flow, which is used as a passive scalar measured by the system. Authors used turbulent pulsations at the interface of two concurrent flows with identical velocities in a square channel as a signal source for the correlation method. The paper presents the methodology of the tests, test facility description, signalto-noise ratio estimation, the results of digital signal processing and comparison of the measured velocities in the model with the flowrate‒averaged velocity determined by the use of flowmeters. The measured velocity values give acceptable agreement for the turbulent flow modes. It was shown that the measurement accuracy drops sharply for low-Reynolds flows.The obtained results were used for flowrate measurements in core-imitator channels of the nuclear reactor test model. The presented paper is an approbation of this approach for its application as part of an test model of a nuclear reactor in order to determine the each duct flow rates in the channels of the core simulator using wire mesh sensors.https://pimi.bntu.by/jour/article/view/663measuring systemcorrelation flowmeterspatial conductometrymodeling of processes in the elements of nuclear power units
spellingShingle I. A. Konovalov
A. E. Khrobostov
M. A. Legchanov
D. N. Solncev
A. A. Barinov
A. V. Ryazanov
A. A. Chesnokov
M. A. Makarov
Application of the Correlation Velocity Measurements for Hydrodynamic Investigations of Turbulent Coolant Flow in Nuclear Reactor Elements
Приборы и методы измерений
measuring system
correlation flowmeter
spatial conductometry
modeling of processes in the elements of nuclear power units
title Application of the Correlation Velocity Measurements for Hydrodynamic Investigations of Turbulent Coolant Flow in Nuclear Reactor Elements
title_full Application of the Correlation Velocity Measurements for Hydrodynamic Investigations of Turbulent Coolant Flow in Nuclear Reactor Elements
title_fullStr Application of the Correlation Velocity Measurements for Hydrodynamic Investigations of Turbulent Coolant Flow in Nuclear Reactor Elements
title_full_unstemmed Application of the Correlation Velocity Measurements for Hydrodynamic Investigations of Turbulent Coolant Flow in Nuclear Reactor Elements
title_short Application of the Correlation Velocity Measurements for Hydrodynamic Investigations of Turbulent Coolant Flow in Nuclear Reactor Elements
title_sort application of the correlation velocity measurements for hydrodynamic investigations of turbulent coolant flow in nuclear reactor elements
topic measuring system
correlation flowmeter
spatial conductometry
modeling of processes in the elements of nuclear power units
url https://pimi.bntu.by/jour/article/view/663
work_keys_str_mv AT iakonovalov applicationofthecorrelationvelocitymeasurementsforhydrodynamicinvestigationsofturbulentcoolantflowinnuclearreactorelements
AT aekhrobostov applicationofthecorrelationvelocitymeasurementsforhydrodynamicinvestigationsofturbulentcoolantflowinnuclearreactorelements
AT malegchanov applicationofthecorrelationvelocitymeasurementsforhydrodynamicinvestigationsofturbulentcoolantflowinnuclearreactorelements
AT dnsolncev applicationofthecorrelationvelocitymeasurementsforhydrodynamicinvestigationsofturbulentcoolantflowinnuclearreactorelements
AT aabarinov applicationofthecorrelationvelocitymeasurementsforhydrodynamicinvestigationsofturbulentcoolantflowinnuclearreactorelements
AT avryazanov applicationofthecorrelationvelocitymeasurementsforhydrodynamicinvestigationsofturbulentcoolantflowinnuclearreactorelements
AT aachesnokov applicationofthecorrelationvelocitymeasurementsforhydrodynamicinvestigationsofturbulentcoolantflowinnuclearreactorelements
AT mamakarov applicationofthecorrelationvelocitymeasurementsforhydrodynamicinvestigationsofturbulentcoolantflowinnuclearreactorelements