Zobrazeno 1 - 10
of 15
pro vyhledávání: '"I. V. Elkin"'
Autor:
A. Del Nevo, M. Adorni, F. D'Auria, O. I. Melikhov, I. V. Elkin, V. I. Schekoldin, M. O. Zakutaev, S. I. Zaitsev, M. Benčík
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000. Five exp
Externí odkaz:
https://doaj.org/article/e7ad943862cf478ab505d0bc05fb99fa
Autor:
Oleg I. Melikhov, A. V. Kapustin, G J Volkov, I. V. Elkin, V.I. Melikhov, S M Nikonov, O. N. Trubkin
Publikováno v:
Thermal Engineering. 68:142-151
Experience gained from the operation of nuclear power plants shows that emergencies or incorrect actions of the personnel may give rise to water hammer phenomena, which exert additional impacts on the pipelines and equipment. Condensation-induced wat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::929c9366167ffe194db6b076d4e3c70e
https://doi.org/10.1134/s0040601521020087
https://doi.org/10.1134/s0040601521020087
Autor:
Yu. V. Parfenov, S M Nikonov, D. A. Emelianov, V. I. Melikhov, I. V. Elkin, A. A. Nerovnov, Oleg I. Melikhov, V. N. Blinkov
Publikováno v:
Thermal Engineering. 63:51-55
The results of a calculation and experimental research of the influence of nonuniformity of the submerged perforated sheet on steam demand leveling on the evaporation surface are published in the current article. A short description of the PGV test f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8231b11f8a508f8d65ea460611e8c1c7
https://doi.org/10.1134/s0040601515120034
https://doi.org/10.1134/s0040601515120034
Autor:
Oleg I. Melikhov, A. A. Nerovnov, V. N. Blinkov, V. I. Melikhov, I. V. Elkin, S M Nikonov, Yu. V. Parfenov, D. A. Emelianov
Publikováno v:
Thermal Engineering. 62:484-489
The results from an experimental investigation of two-phase flow motion through a submerged perforated sheet (SPS) obtained at the Elektrogorsk Research Center test facility are presented. The test facility, the test section of which is a transverse
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::286fb8cff34c339ba1bcab49b16af0d7
https://doi.org/10.1134/s0040601515070010
https://doi.org/10.1134/s0040601515070010
Publikováno v:
Nuclear Engineering and Design. 250:633-645
VVER 1000 reactors have some unique and specific features (e.g. large primary and secondary side fluid inventory, horizontal steam generators, core design) that require dedicated experimental and analytical analyses in order to assess the performance
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b40e05a734f1a95cb500b66226a3f58f
https://doi.org/10.1016/j.nucengdes.2012.06.027
https://doi.org/10.1016/j.nucengdes.2012.06.027
Publikováno v:
Thermal Engineering. 57:213-218
Prospects for enhancing heat transfer in the core of reactor plants by using annular fuel elements are considered. Advantages of changing over to use of annular fuel elements are analyzed, and problems that must be solved are identified. It is shown
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::626763d51a8afc298c40fab89b542027
https://doi.org/10.1134/s0040601510030043
https://doi.org/10.1134/s0040601510030043
Publikováno v:
Power Technology and Engineering. 41:351-354
Results of experiments conducted on a large-scale integral PSB-VVER bench and directed toward investigation of the performance of new passive safety systems for nuclear plants with a water-cooled power reactor, an additional system for passive floodi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f5a43b29cbbb89568fb15f0af6d855e6
https://doi.org/10.1007/s10749-007-0063-7
https://doi.org/10.1007/s10749-007-0063-7
Publikováno v:
Atomic Energy. 95:765-770
Five standard problems of investigating accidents with loss of coolant in the first loop are studied for the first time on the basis of experiments which were performed in 1993–2001 on the ISB-VVER two-circuit integrated thermophysical stand, simul
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::90767e2f082586a81560d4c329304714
https://doi.org/10.1023/b:aten.0000016761.51115.dd
https://doi.org/10.1023/b:aten.0000016761.51115.dd
Autor:
Oleg I. Melikhov, V. I. Melikhov, Sergey M. Nikonov, Maxim O. Zakutaev, Dmitry I. Dorofeev, Sergey I. Zaitsev, I. V. Elkin, Sergey S. Pylev
Publikováno v:
Volume 2A: Thermal Hydraulics.
In 2012 on the large-scale thermalphysic PSB-VVER facility modelling of three different type accidents is executed: - Guillotine rupture of the pipeline on a reactor inlet; - A small leak from “the cold” pipeline; - Rupture of pressurizer surge l
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34603ca028c60f3c50df252b4eff923d
https://doi.org/10.1115/icone22-30296
https://doi.org/10.1115/icone22-30296
Autor:
I. V. Elkin, S. I. Zaitsev, M. O. Zakutaev, M. Adorni, A. Del Nevo, M. Bencík, V. I. Schekoldin, Oleg I. Melikhov, Francesco Saverio D'Auria
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000. Five exp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::26732d9f43e268bb1f3bb367c4f87e45
http://hdl.handle.net/11568/831248
http://hdl.handle.net/11568/831248
