MATEC Web Conf.
Volume 345, 202120th Conference on Power System Engineering
|Number of page(s)||6|
|Published online||12 October 2021|
Measurement of pressure loss coefficient for nuclear fuel assembly
Škoda JS a.s., Orlík 266, Plzeň, 316 00, Czech Republic
* Corresponding author: Pavel.Nerud@skoda-js.cz
Design and operation of nuclear reactor is very difficult issue from the engineering and technical point of view. All facilities must be availably designed separately, but with respect to other facilities working in the same system too. In nuclear power plant the key safety factor is the insurance of nuclear fuel assemblies cooling. The basic requirement from this point of view is an pressure loss coefficient assessment for all possible modes of coolant flow. This article describes an experience with measurement of pressure loss coefficient characteristics in Škoda JS.
© The Authors, published by EDP Sciences, 2021
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.