Experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactor

Description is given of the methodology for experimental substantiation of hydrodynamic characteristics of imitators of fuel channels in the model of reactor unit with two-loop configuration. It is known from the experience of development of reactor units of different types that it is practically no...

Full description

Bibliographic Details
Main Authors: E.F. Avdeev, I.A. Chusov, Yu. D. Levchenko, Yu. S. Yur'ev
Format: Article
Language:English
Published: National Research Nuclear University (MEPhI) 2015-10-01
Series:Nuclear Energy and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S245230381600008X
id doaj-67f8319ec7d84e6c8f608db2690f583c
record_format Article
spelling doaj-67f8319ec7d84e6c8f608db2690f583c2020-11-25T01:12:43ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382015-10-011213914610.1016/j.nucet.2016.01.007Experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactorE.F. Avdeev0I.A. Chusov1Yu. D. Levchenko2Yu. S. Yur'ev3Obninsk Institute for Nuclear Power Engineering, National Research, Nuclear University «MEPhI». 1, Studgorodok, Obninsk, Kaluga region 249040, RussiaObninsk Institute for Nuclear Power Engineering, National Research, Nuclear University «MEPhI». 1, Studgorodok, Obninsk, Kaluga region 249040, RussiaJSC «State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering n.a. A.I. Lejpunsky». 1, Bondarenko sq., Obninsk, Kaluga region 249033, RussiaJSC «State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering n.a. A.I. Lejpunsky». 1, Bondarenko sq., Obninsk, Kaluga region 249033, RussiaDescription is given of the methodology for experimental substantiation of hydrodynamic characteristics of imitators of fuel channels in the model of reactor unit with two-loop configuration. It is known from the experience of development of reactor units of different types that it is practically not feasible to select the channel to serve as the imitator with simple geometry for which the dependence of pressure drop due to hydraulic losses would be the same as the dependence for full-scale operating fuel channel containing fuel assemblies. Therefore, only approximate modeling of hydraulic losses in operational fuel channels with fuel assemblies and imitating channels within the limited range of Reynolds numbers can be discussed as well as inclusion of all coolant flow regimes within the reactor vessel predicted by design calculations. Selection of final geometry of imitating channels was made based on the following several basic assumptions of approximate modeling of flow path in the full-scale fuel channel with fuel assembly under nominal operational mode of the nuclear reactor using the channel with simplified geometry: (1) range of variation of coolant flow rates in the operational fuel channel with fuel assembly in nominal operational mode of the reactor is known from physical and from preliminary thermal physics calculation studies; (2) equality of Euler numbers for nominal coolant flow regimes in the reactor and for coolant flow in imitating channels. Experiments were conducted with three types of imitators and the most suitable among them was chosen as the result. The finally selected design of imitating channel included a pipe with high-quality of manufacturing, two diaphragms and a nozzle with configured using the method suggested by Vitoshinsky.http://www.sciencedirect.com/science/article/pii/S245230381600008XReactor unitHydraulic resistanceOperational fuel channelImitating channelThermal hydraulic model of nuclear reactorReactor coreFuel assemblyModeling scaleGeometry distortion of the modelEuler numbersReynolds numbers
collection DOAJ
language English
format Article
sources DOAJ
author E.F. Avdeev
I.A. Chusov
Yu. D. Levchenko
Yu. S. Yur'ev
spellingShingle E.F. Avdeev
I.A. Chusov
Yu. D. Levchenko
Yu. S. Yur'ev
Experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactor
Nuclear Energy and Technology
Reactor unit
Hydraulic resistance
Operational fuel channel
Imitating channel
Thermal hydraulic model of nuclear reactor
Reactor core
Fuel assembly
Modeling scale
Geometry distortion of the model
Euler numbers
Reynolds numbers
author_facet E.F. Avdeev
I.A. Chusov
Yu. D. Levchenko
Yu. S. Yur'ev
author_sort E.F. Avdeev
title Experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactor
title_short Experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactor
title_full Experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactor
title_fullStr Experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactor
title_full_unstemmed Experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactor
title_sort experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactor
publisher National Research Nuclear University (MEPhI)
series Nuclear Energy and Technology
issn 2452-3038
publishDate 2015-10-01
description Description is given of the methodology for experimental substantiation of hydrodynamic characteristics of imitators of fuel channels in the model of reactor unit with two-loop configuration. It is known from the experience of development of reactor units of different types that it is practically not feasible to select the channel to serve as the imitator with simple geometry for which the dependence of pressure drop due to hydraulic losses would be the same as the dependence for full-scale operating fuel channel containing fuel assemblies. Therefore, only approximate modeling of hydraulic losses in operational fuel channels with fuel assemblies and imitating channels within the limited range of Reynolds numbers can be discussed as well as inclusion of all coolant flow regimes within the reactor vessel predicted by design calculations. Selection of final geometry of imitating channels was made based on the following several basic assumptions of approximate modeling of flow path in the full-scale fuel channel with fuel assembly under nominal operational mode of the nuclear reactor using the channel with simplified geometry: (1) range of variation of coolant flow rates in the operational fuel channel with fuel assembly in nominal operational mode of the reactor is known from physical and from preliminary thermal physics calculation studies; (2) equality of Euler numbers for nominal coolant flow regimes in the reactor and for coolant flow in imitating channels. Experiments were conducted with three types of imitators and the most suitable among them was chosen as the result. The finally selected design of imitating channel included a pipe with high-quality of manufacturing, two diaphragms and a nozzle with configured using the method suggested by Vitoshinsky.
topic Reactor unit
Hydraulic resistance
Operational fuel channel
Imitating channel
Thermal hydraulic model of nuclear reactor
Reactor core
Fuel assembly
Modeling scale
Geometry distortion of the model
Euler numbers
Reynolds numbers
url http://www.sciencedirect.com/science/article/pii/S245230381600008X
work_keys_str_mv AT efavdeev experimentalsubstantiationofselectionoffuelchannelimitatorforhydrodynamicmodelofnuclearreactor
AT iachusov experimentalsubstantiationofselectionoffuelchannelimitatorforhydrodynamicmodelofnuclearreactor
AT yudlevchenko experimentalsubstantiationofselectionoffuelchannelimitatorforhydrodynamicmodelofnuclearreactor
AT yusyurev experimentalsubstantiationofselectionoffuelchannelimitatorforhydrodynamicmodelofnuclearreactor
_version_ 1725165426950799360