Zobrazeno 1 - 10
of 23
pro vyhledávání: '"A. E. Kisselev"'
Autor:
Dinara A. Kazbaeva, Ruslan R. Zhdanov, Arkadiy M. Komissarov, Aydar I. Salikhov, Anton E. Kisselev
Publikováno v:
SPIE Proceedings.
Optical Reflectometer (OTDR-Optical Time Domain Reflectometr) of various types are widely used in almost all stages of the fiber-optic communication systems, from production of fiber optic cable to the construction of fiber-optic communication lines
Publikováno v:
Atomic Energy. 114:161-168
Some results of a numerical analysis of the serious unanticipated accident at the Fukishima-1 NPP are presented. The analysis was performed in March 2011 as part of the support given by Rosatom, including in making decisions about possible protection
Publikováno v:
Atomic Energy. 114:102-107
During the serious accident at the Fukushima-1 NPP (Japan), the cores of the Nos. 2 and 3 units were cooled for a long period of time by safety systems which were not designed for operation under prolonged power loss. The serviceability of BWR-4 high
Publikováno v:
Nuclear Engineering and Design. 246:175-184
The PARAMETER-SF4 test conditions simulated a severe LOCA (loss of coolant accident) NPP (nuclear power plant) sequence in which the overheated core up to 1700–2300 K would be reflooded from the bottom on ECCS (emergency core cooling system) recove
Autor:
Tim Haste, Mirco Grosse, N. Vér, Martin Steinbrück, Juri Stuckert, A. E. Kisselev, Zoltán Hózer, L. Sepold, J. Birchley, A. V. Goryachev, V. P. Semishkin, V. I. Nalivaev, M.S. Veshchunov, A.V. Boldyrev
Publikováno v:
Progress in Nuclear Energy. 52:19-36
This paper gives an overview on the status of knowledge of high-temperature oxidation of the two zirconium alloys Zircaloy-4 and E110 with special emphasis on results obtained during the SARNET period. The tin-bearing alloy Zircaloy-4 and the niobium
Publikováno v:
Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security.
The problem of reactor pressure vessel (RPV) integrity during in-vessel melt retention for VVER type reactor is considered. Comprehensive numerical analysis contains the modeling of full severe accident scenario including thermal and mechanical loads
Autor:
Alexander D. Vasiliev, Valerii F. Strizhov, Vladimir I. Nalivayev, Nikolay Ya. Parshin, Arcadii E. Kisselev
Publikováno v:
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance.
The PARAMETER-SF3 test conditions simulated a severe LOCA (Loss of Coolant Accident) nuclear power plant sequence in which the overheated up to 1700÷2300K core would be reflooded from the top and the bottom in occasion of ECCS (Emergency Core Coolin