Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213

To safely and efficiently load the fuel assemblies of the VVER 440 / V 213 nuclear reactor, the relation between the temperature of the coolant at the outlet of the fuel assembly, measured by a thermocouple in the assembly’s axis, and the mean coolant temperature, present in the plane of the thermoc...

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Main Authors:	Mlynár Peter, Világi František, Závodný Zdenko, Urban František, Ridzoň František
Format:	Article
Language:	English
Published:	EDP Sciences 2020-01-01
Series:	MATEC Web of Conferences
Online Access:	https://www.matec-conferences.org/articles/matecconf/pdf/2020/24/matecconf_aenmfme2020_01010.pdf

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spelling	doaj-287cdd601e3c4590b1c1b60ad5957e762021-08-05T13:52:45ZengEDP SciencesMATEC Web of Conferences2261-236X2020-01-013280101010.1051/matecconf/202032801010matecconf_aenmfme2020_01010Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213Mlynár Peter0Világi František1Závodný Zdenko2Urban František3Ridzoň František4Slovak University of Technology in Bratislava, Faculty of Mechanical Engineering, Institute of Energy MachinerySlovak University of Technology in Bratislava, Faculty of Mechanical Engineering, Institute of Energy MachinerySlovak University of Technology in Bratislava, Faculty of Mechanical Engineering, Institute of Energy MachinerySlovak University of Technology in Bratislava, Faculty of Mechanical Engineering, Institute of Energy MachinerySlovak University of Technology in Bratislava, Faculty of Mechanical Engineering, Institute of Energy MachineryTo safely and efficiently load the fuel assemblies of the VVER 440 / V 213 nuclear reactor, the relation between the temperature of the coolant at the outlet of the fuel assembly, measured by a thermocouple in the assembly’s axis, and the mean coolant temperature, present in the plane of the thermocouple, must be analysed. Based on the analysis of the coolant flow at the output of the physical model of the fuel assembly I. [1] and published CFD simulations [2,3,4] it was shown, that a special attention has to be paid to the influence of the water flow in the central tube on the temperature and velocity profile of the coolant at the thermocouple’s plane in the fuel assembly. For this reason, an experimental device with a physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V 213 was designed, manufactured, and operated at the Faculty of Mechanical Engineering STU in Bratislava.https://www.matec-conferences.org/articles/matecconf/pdf/2020/24/matecconf_aenmfme2020_01010.pdf
collection	DOAJ
language	English
format	Article
sources	DOAJ
author	Mlynár Peter Világi František Závodný Zdenko Urban František Ridzoň František
spellingShingle	Mlynár Peter Világi František Závodný Zdenko Urban František Ridzoň František Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213 MATEC Web of Conferences
author_facet	Mlynár Peter Világi František Závodný Zdenko Urban František Ridzoň František
author_sort	Mlynár Peter
title	Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213
title_short	Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213
title_full	Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213
title_fullStr	Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213
title_full_unstemmed	Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213
title_sort	analysis of coolant flow at the outlet of the physical model of the fuel assembly ii. of the nuclear reactor vver 440 / v213
publisher	EDP Sciences
series	MATEC Web of Conferences
issn	2261-236X
publishDate	2020-01-01
description	To safely and efficiently load the fuel assemblies of the VVER 440 / V 213 nuclear reactor, the relation between the temperature of the coolant at the outlet of the fuel assembly, measured by a thermocouple in the assembly’s axis, and the mean coolant temperature, present in the plane of the thermocouple, must be analysed. Based on the analysis of the coolant flow at the output of the physical model of the fuel assembly I. [1] and published CFD simulations [2,3,4] it was shown, that a special attention has to be paid to the influence of the water flow in the central tube on the temperature and velocity profile of the coolant at the thermocouple’s plane in the fuel assembly. For this reason, an experimental device with a physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V 213 was designed, manufactured, and operated at the Faculty of Mechanical Engineering STU in Bratislava.
url	https://www.matec-conferences.org/articles/matecconf/pdf/2020/24/matecconf_aenmfme2020_01010.pdf
work_keys_str_mv	AT mlynarpeter analysisofcoolantflowattheoutletofthephysicalmodelofthefuelassemblyiiofthenuclearreactorvver440v213 AT vilagifrantisek analysisofcoolantflowattheoutletofthephysicalmodelofthefuelassemblyiiofthenuclearreactorvver440v213 AT zavodnyzdenko analysisofcoolantflowattheoutletofthephysicalmodelofthefuelassemblyiiofthenuclearreactorvver440v213 AT urbanfrantisek analysisofcoolantflowattheoutletofthephysicalmodelofthefuelassemblyiiofthenuclearreactorvver440v213 AT ridzonfrantisek analysisofcoolantflowattheoutletofthephysicalmodelofthefuelassemblyiiofthenuclearreactorvver440v213
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Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213

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