Determination of the Flow Rate of Coolant in Pipelines with Unstabilized Flow of Fluid in the Area Following a Bend
- Autores: Boltenko É.1, Davydov M.1, Korol’kov B.1, Basov A.1, Kononenko I.1, Sharov V.1
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Afiliações:
- Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
- Edição: Volume 51, Nº 5 (2018)
- Páginas: 562-567
- Seção: Article
- URL: https://journals.rcsi.science/1570-145X/article/view/245955
- DOI: https://doi.org/10.1007/s10749-018-0874-8
- ID: 245955
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Resumo
Questions related to the determination of the flow rate of coolant in the pipelines of electric plants are considered. Amethod of determining the flow of single-phase coolant for the case of an asymmetric unstabilized velocity profile that is present following a bend in a pipeline is proposed. Results from the use of the proposed method in novel experiments on the testing unit of the Élektrogorsk Scientific Research Center and in the steam pipelines of power unit No. 3 of the Balakovo nuclear power plant are presented.
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Sobre autores
É. Boltenko
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Rússia, Moscow oblast’
M. Davydov
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Autor responsável pela correspondência
Email: mike.davydov@erec.ru
Rússia, Moscow oblast’
B. Korol’kov
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Rússia, Moscow oblast’
A. Basov
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Rússia, Moscow oblast’
I. Kononenko
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Rússia, Moscow oblast’
V. Sharov
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Rússia, Moscow oblast’