Determination of the Flow Rate of Coolant in Pipelines with Unstabilized Flow of Fluid in the Area Following a Bend
- Авторлар: Boltenko É.1, Davydov M.1, Korol’kov B.1, Basov A.1, Kononenko I.1, Sharov V.1
-
Мекемелер:
- Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
- Шығарылым: Том 51, № 5 (2018)
- Беттер: 562-567
- Бөлім: Article
- URL: https://journals.rcsi.science/1570-145X/article/view/245955
- DOI: https://doi.org/10.1007/s10749-018-0874-8
- ID: 245955
Дәйексөз келтіру
Аннотация
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.
Негізгі сөздер
Авторлар туралы
É. Boltenko
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Ресей, Moscow oblast’
M. Davydov
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Хат алмасуға жауапты Автор.
Email: mike.davydov@erec.ru
Ресей, Moscow oblast’
B. Korol’kov
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Ресей, Moscow oblast’
A. Basov
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Ресей, Moscow oblast’
I. Kononenko
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Ресей, Moscow oblast’
V. Sharov
Élektrogorsk Scientific Research Center on the Safety of Nuclear Power Plants
Email: mike.davydov@erec.ru
Ресей, Moscow oblast’