MATEC Web Conf.
Volume 328, 2020XXII. International Scientific Conference – The Application of Experimental and Numerical Methods in Fluid Mechanics and Energy 2020 (AEaNMiFMaE-2020)
|Number of page(s)||12|
|Section||Measurement and Calculation of State Variables in the Fluid Flow|
|Published online||18 November 2020|
Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213
Slovak University of Technology in Bratislava, Faculty of Mechanical Engineering, Institute of Energy Machinery, Nám. slobody 17, 812 31 Bratislava, Slovakia
* Corresponding author: email@example.com
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.  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.
© The Authors, published by EDP Sciences, 2020
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