Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions

Juraj Paulech; Vladimír Kutiš; Gabriel Gálik; Jakub Jakubec; Tibor Sedlár

doi:10.1515/scjme-2017-0009

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Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions

Strojnícky časopis - Journal of Mechanical Engineering

Volume 67 (2017): Issue 1 (April 2017)

By: Juraj Paulech, Vladimír Kutiš, Gabriel Gálik, Jakub Jakubec and Tibor Sedlár

Open Access

|May 2017

Abstract

The paper presents the numerical simulation of thermo-hydraulic behaviour of coolant in the VVER- 440 nuclear reactor under standard outage conditions. Heating-up and flow of coolant between the reactor pressure vessel and spent fuel storage pool are discussed.

References

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Articles in this issue

DOI: https://doi.org/10.1515/scjme-2017-0009 | Journal eISSN: 2450-5471 | Journal ISSN: 0039-2472

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Language: English

Page range: 87 - 92

Published on: May 3, 2017

Published by: Slovak University of Technology in Bratislava

In partnership with: Paradigm Publishing Services

Publication frequency: 2 issues per year

Keywords:

Related subjects:

Mechanical engineering,

Fundamentals of mechanical engineering,

Mechanics

© 2017 Juraj Paulech, Vladimír Kutiš, Gabriel Gálik, Jakub Jakubec, Tibor Sedlár, published by Slovak University of Technology in Bratislava
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

Volume 67 (2017): Issue 1 (April 2017)