Zobrazeno 1 - 10
of 121
pro vyhledávání: '"Vurim, A."'
Autor:
Kelsingazina, Ruziya, Vityuk, Vladimir, Vurim, Alexander, Vityuk, Galina, Mukhamedov, Nurzhan, Tikhomirov, Georgy
Publikováno v:
In Annals of Nuclear Energy 1 September 2024 204
Publikováno v:
AIMS Materials Science, Vol 10, Iss 6, Pp 1034-1044 (2023)
In this article, we present the results of the creation of an information-analytical system (IAS) developed as a tool for research and prediction of the behavior of the corium simulating a core melt of a nuclear reactor in the experiments. This was c
Externí odkaz:
https://doaj.org/article/ae6b802de5c74c1e90387529d76c1dbd
Publikováno v:
In Nuclear Engineering and Design 15 December 2023 415
Autor:
Imaizumi, Yuya, Aoyagi, Mitsuhiro, Kamiyama, Kenji, Matsuba, Ken-ichi, Akaev, Assan, Mikisha, Anatoly, Baklanov, Viktor, Vurim, Alexandr
Publikováno v:
In Annals of Nuclear Energy 15 December 2023 194
Autor:
Ruslan А. Irkimbekov, Artur S. Surayev, Galina А. Vityuk, Olzhas M. Zhanbolatov, Zamanbek B. Kozhabaev, Sergey V. Bedenko, Nima Ghal-Eh, Alexander D. Vurim
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 4, Pp 1439-1447 (2023)
The fuel cycle characteristics of the IVG.1M reactor were studied within the framework of the research reactor conversion program to modernize the IVG.1M reactor. Optimum use of the nuclear fuel and reactor was achieved through routine methods which
Externí odkaz:
https://doaj.org/article/256892d3bb924e0d96f1b204579f69ed
Autor:
Vityuk, Vladimir, Vityuk, Galina, Vurim, Alexander, Irkimbekov, Ruslan, Kukushkin, Ivan, Surayev, Artur, Mukhamedov, Nurzhan
Publikováno v:
In Progress in Nuclear Energy October 2023 164
Autor:
Irkimbekov, Ruslan А., Surayev, Artur S., Vityuk, Galina А., Zhanbolatov, Olzhas M., Kozhabaev, Zamanbek B., Bedenko, Sergey V., Ghal-Eh, Nima, Vurim, Alexander D.
Publikováno v:
In Nuclear Engineering and Technology April 2023 55(4):1439-1447
Publikováno v:
In Annals of Nuclear Energy March 2023 182
Publikováno v:
Eurasian Journal of Physics and Functional Materials, Vol 6, Iss 3, Pp 198-212 (2022)
The article presents the results of computational studies to substantiate the possibility of testing the fuel of the Multipurpose hYbrid Research Reactor for a High-tech Applications reactor (MYRRHA) in the Impulse Graphite research Reactor (IGR). A
Externí odkaz:
https://doaj.org/article/29e3d9a1b18c46f1a819a90d74e470cb
Autor:
Ruslan A. Irkimbekov, Aleksandr D. Vurim, Sergey V. Bedenko, Artur S. Surayev, Galina A. Vityuk
Publikováno v:
Nuclear Energy and Technology, Vol 8, Iss 3, Pp 167-172 (2022)
IVG.1M is a research pressurized water reactor designed to use high-enriched fuel. As part of the core conversion program, the reactor will be switched to a new low-enriched composite uranium fuel. Further operation of the reactor is determined by th
Externí odkaz:
https://doaj.org/article/48d7b7d0cdf7484693f31a833d45209b