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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Bibliographic Details
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