Zobrazeno 1 - 10
of 24
pro vyhledávání: '"Nerovnov, A."'
Publikováno v:
In Nuclear Engineering and Design January 2020 356
Publikováno v:
Thermal Engineering. 65:45-50
Processing of experimental data on the pressure difference across a submerged perforated sheet (SPS) revealed that, at sufficiently high void fractions under SPS, the pressure difference across it became less than the pressure difference for the pure
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2011 (2011)
The horizontal steam generator (SG) is one of specific features of Russian-type pressurized water reactors (VVERs). The main advantages of horizontal steam generator are connected with low steam loads on evaporation surface, simple separation scheme
Externí odkaz:
https://doaj.org/article/6a508856b48f4be9853bae0b09cb0081
Akademický článek
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Akademický článek
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Publikováno v:
Vestnik MEI. :23-27
Тhe article analyzes the effect the interfacial force interaction models developed for different types of bubble flows have on the bubble layer description. The analysis is performed in the framework of a stationary 1D two-velocity mathematical mode
Publikováno v:
Journal of Physics: Conference Series. 1683:022069
Non-uniform heat transfer occurs at the steam generator secondary side, thus inducing a non-uniform steam generation and a non-uniform steam flow rate along the evaporation surface. In order to equalize the steam flow rate, submerged perforated sheet
Publikováno v:
Annals of Nuclear Energy. 148:107715
The results of a study on the equalization of a non-uniform steam load using submerged perforated sheets (SPSs) are presented. The experimental data obtained at the PGV test facility and calculations performed using the STEG code are used. The PGV te
Publikováno v:
Journal of Physics: Conference Series. 1652:012017
The new model of interfacial drag is proposed and implemented in the STEG code based on the 3D two-fluid model is presented. Experimental data obtained at the PGV test facility is used for validation of the modified STEG code. The PGV test facility c
Publikováno v:
Nuclear Engineering and Design. 356:110380
The results of the validation of the STEG code using the experiments on the PGV test facility are presented. The PGV test facility (Electrogorsk, Russia) is a slice of the upper part of the horizontal steam generator for Russian type VVER reactors. T