Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly

An innovative core with an increased energy resource was used when designing RITM-200 reactor unit. The paper presents the results of experimental and numerical simulation of hydrodynamic processes occurring in the inlet region of the RITM reactor fuel assembly model. Computational mesh of fuel asse...

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Main Authors:	Dmitriev Sergei, Khrobostov Alexander, Legchanov Maksim, Dobrov Alexander
Format:	Article
Language:	English
Published:	EDP Sciences 2018-01-01
Series:	MATEC Web of Conferences
Online Access:	https://doi.org/10.1051/matecconf/201824509017

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record_format	Article
spelling	doaj-db0ec9f47b054cbc8fdc86db05a842662021-02-02T00:10:54ZengEDP SciencesMATEC Web of Conferences2261-236X2018-01-012450901710.1051/matecconf/201824509017matecconf_eece2018_09017Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assemblyDmitriev Sergei0Khrobostov Alexander1Legchanov Maksim2Dobrov Alexander3Nizhniy Novgorod State Technical University n.a. R.E. AlekseevNizhniy Novgorod State Technical University n.a. R.E. AlekseevNizhniy Novgorod State Technical University n.a. R.E. AlekseevNizhniy Novgorod State Technical University n.a. R.E. AlekseevAn innovative core with an increased energy resource was used when designing RITM-200 reactor unit. The paper presents the results of experimental and numerical simulation of hydrodynamic processes occurring in the inlet region of the RITM reactor fuel assembly model. Computational mesh of fuel assembly, containing ~ 22 million elements was created using Ansys ICEM CFD. The values of relative axial velocities in several cross sections at the inlet to the bundle of fuel elements are obtained. At the inlet to the fuel rods bundle the velocity field is not uniform, due to the complex geometry of the fuel assembly. The obtained results of CFD-simulation can be used to determine the input boundary conditions for subchannel programs of the core thermal-hydraulic analysis. This allows taking into account uneven flow rate distribution in subchannels due to the complex geometry of the fuel assembly inlet region.https://doi.org/10.1051/matecconf/201824509017
collection	DOAJ
language	English
format	Article
sources	DOAJ
author	Dmitriev Sergei Khrobostov Alexander Legchanov Maksim Dobrov Alexander
spellingShingle	Dmitriev Sergei Khrobostov Alexander Legchanov Maksim Dobrov Alexander Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly MATEC Web of Conferences
author_facet	Dmitriev Sergei Khrobostov Alexander Legchanov Maksim Dobrov Alexander
author_sort	Dmitriev Sergei
title	Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly
title_short	Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly
title_full	Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly
title_fullStr	Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly
title_full_unstemmed	Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly
title_sort	experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly
publisher	EDP Sciences
series	MATEC Web of Conferences
issn	2261-236X
publishDate	2018-01-01
description	An innovative core with an increased energy resource was used when designing RITM-200 reactor unit. The paper presents the results of experimental and numerical simulation of hydrodynamic processes occurring in the inlet region of the RITM reactor fuel assembly model. Computational mesh of fuel assembly, containing ~ 22 million elements was created using Ansys ICEM CFD. The values of relative axial velocities in several cross sections at the inlet to the bundle of fuel elements are obtained. At the inlet to the fuel rods bundle the velocity field is not uniform, due to the complex geometry of the fuel assembly. The obtained results of CFD-simulation can be used to determine the input boundary conditions for subchannel programs of the core thermal-hydraulic analysis. This allows taking into account uneven flow rate distribution in subchannels due to the complex geometry of the fuel assembly inlet region.
url	https://doi.org/10.1051/matecconf/201824509017
work_keys_str_mv	AT dmitrievsergei experimentalstudiesandnumericalsimulationofcoolanthydrodynamicsintheinletareaofnuclearreactorfuelassembly AT khrobostovalexander experimentalstudiesandnumericalsimulationofcoolanthydrodynamicsintheinletareaofnuclearreactorfuelassembly AT legchanovmaksim experimentalstudiesandnumericalsimulationofcoolanthydrodynamicsintheinletareaofnuclearreactorfuelassembly AT dobrovalexander experimentalstudiesandnumericalsimulationofcoolanthydrodynamicsintheinletareaofnuclearreactorfuelassembly
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Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly

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