| Issue |
MATEC Web Conf.
Volume 345, 2021
20th Conference on Power System Engineering
|
|
|---|---|---|
| Article Number | 00023 | |
| Number of page(s) | 6 | |
| DOI | https://doi.org/10.1051/matecconf/202134500023 | |
| 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.
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