Zobrazeno 1 - 10
of 30
pro vyhledávání: '"E.G. Kuzmin"'
Autor:
A.L. Modyaev, M.M. Sokolov, I.V. Levin, E.G. Kuzmin, A.V. Lutchenko, D.M. Sidorenko, G. E. Notkin, A.P. Khvostenko, A.V. Nikolaev, N.V. Injutin, A.N. Romannikov, A.V. Solopeko, V.A. Kochin, I.O. Anashkin, E.N. Bondarchuk, A. V. Sushkov, P.P. Khvostenko
Publikováno v:
Fusion Engineering and Design. 146:1108-1112
At the present time, in the NRC Kurchatov Institute under the auspices of the Federal Target Program “Nuclear energy-technologies of new generation for period 2010–2015 and to the prospect until 2020” the tokamak T-15MD and supporting facilitie
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5d0728af9861d82c65b00aed294dbb99
https://doi.org/10.1016/j.fusengdes.2019.02.018
https://doi.org/10.1016/j.fusengdes.2019.02.018
Autor:
E.N. Bondarchuk, D. A. Karpov, V.I. Tanchuk, A.P. Khvostenko, A.V. Nikolaev, M. M. Sokolov, N.V. Injutin, A.G. Kachkin, E.G. Kuzmin, A.V. Lutchenko, A.A. Niyazov, V.A. Kochin, P.P. Khvostenko, M.V. Chukanov, I.O. Anashkin, A.V. Solopeko, K.V. Borisenko, I.S. Obraztsov, D.M. Sidorenko, G.S. Kuzmina
Publikováno v:
Fusion Engineering and Design. 146:2205-2208
Presently, the Tokamak T-15MD is being built in the NRC “Kurchatov Institute”. The vacuum vessel was manufactured and passed the preliminary vacuum tests at the plant in St. Petersburg (Efremov Institute) in 2016. Vacuum vessel consists of toroid
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::36a7620d5d96c918d8823d6ad109677d
https://doi.org/10.1016/j.fusengdes.2019.03.153
https://doi.org/10.1016/j.fusengdes.2019.03.153
Autor:
N. A. Kirneva, A.N. Romannikov, A.N. Chudnovsky, V.M. Leonov, M. M. Sokolov, I. N. Roy, A. A. Kavin, A.L. Modyaev, I.V. Levin, G. E. Notkin, P.P. Khvostenko, E.G. Kuzmin, A.V. Lutchenko, A.P. Khvostenko, A.V. Nikolaev, E.N. Bondarchuk, A. V. Sushkov, I.O. Anashkin
Publikováno v:
Fusion Engineering and Design. 164:112211
At the present time, the preparation to physical start-up of tokamak T-15MD is completed in the National Research Center “Kurchatov Institute”. The main parameters of T-15MD are: R = 1.48 m, a = 0.67 m, B = 2.0 T, Ipl = 2.0 MA. The magnet system
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f3fbb36599055d7fc3ad0ba28b02806d
https://doi.org/10.1016/j.fusengdes.2020.112211
https://doi.org/10.1016/j.fusengdes.2020.112211
Autor:
E.G. Kuzmin, V. A. Kochin, P.P. Khvostenko, V. V. Klyuev, I. A. Mironov, V. A. Krylov, A. B. Mineev, V. A. Alkhimovich, Victor Tanchuk, Sergey Grigoriev
Publikováno v:
Plasma Devices and Operations. 12:19-30
The paper describes the Vacuum vessel (VV) designed for plasma experiments on the T-15M tokamak. The main parameters, design and features of the VV and in-vessel components are presented. VV is a thin-walled shell made of stainless steel like AISI 32
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::479515fc52794142c72ece3a472bba4c
https://doi.org/10.1080/10519990310001604281
https://doi.org/10.1080/10519990310001604281
Autor:
V. A. Korotkov, V. N. Dokuka, Yu. P. Arefiev, R.R. Khayrutdinov, E.G. Kuzmin, N. A. Obysov, A. V. Lopatkin, V. M. Komarov, G. G. Gladush, O. G. Filatov, E. A. Azizov, V. A. Krylov, V. G. Muratov, Vladimir Filatov, V. A. Yagnov, A. B. Mineev, I. V. Mazul
Publikováno v:
Plasma Devices and Operations. 11:279-286
By concept development of the compact volumetric neutron source on the spherical tokamak JUST basis for minor actinides transmutation with aspect ratio A = 2, some key plasma physics problems are arising: start of discharge; plasma current maintenanc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eb235d4b8d4e52f8ee867746cff1be93
https://doi.org/10.1080/1051999031000155515
https://doi.org/10.1080/1051999031000155515
Publikováno v:
Fusion Engineering and Design. :185-190
Joining of tungsten with copper-based cooling structure and armour geometry optimization are the major aspects in development of the tungsten-armoured plasma facing components (PFC). Fabrication techniques and high heat flux (HHF) tests of tungsten-a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5564bc3f920f4e9dbef311cf716051a6
https://doi.org/10.1016/s0920-3796(02)00297-1
https://doi.org/10.1016/s0920-3796(02)00297-1
Autor:
K. A. Podushnikova, I. N. Leikin, N.Ya. Dvorkin, V.V. Mikov, A. N. Novokhatskii, K. G. Shakhovets, I. A. Mironov, E.G. Kuzmin, V. B. Minaev, V. V. Shpeizman
Publikováno v:
Plasma Devices and Operations. 9:83-94
Fabrication and assembly of the vacuum vessel of the spherical tokamak Globus-M are described. The development of new technological procedures required for the vessel fabrication is outlined. Manufacturing of the vacuum vessel shell of the tokamak wa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2ae8f5aec83c14f8c61faade46391140
https://doi.org/10.1080/10519990108224488
https://doi.org/10.1080/10519990108224488
Autor:
I. N. Leykin, V.P. Shestakov, E.G. Kuzmin, E. A. Azizov, V. A. Yagnov, A. B. Mineev, I.L. Tazhibaeva, N.Ya. Dvorkin, R.R. Khayrutdinov, V. A. Krylov, Yu.S. Cherepnin, G. V. Shapovalov, V. S. Shkolnik, V. N. Dokouka, V. A. Korotkov, L. N. Tikhomirov
Publikováno v:
Fusion Engineering and Design. :831-835
The construction of a special machine for plasma facing material testing under powerful and particle and heat flux deposition is necessary for progress of researches in the field of controlled fusion to industrial application. Kazakhstan tokamak for
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::20d40f2b3425660d71d6b43a42e62ee2
https://doi.org/10.1016/s0920-3796(01)00361-1
https://doi.org/10.1016/s0920-3796(01)00361-1
Autor:
V. A. Belyakov, V. A. Yagnov, V. E. Golant, E. E. Mukhin, V. V. D’yachenko, E. N. Tregubova, V. K. Gusev, A. N. Novokhatskii, G. T. Razdobarin, V. B. Minaev, V.F. Soikin, Yu. A. Kostsov, O. N. Shcherbinin, E.G. Kuzmin, E.A. Kuznetsov, K. A. Podushnikova, M. A. Irzak, V. S. Uzlov, A. A. Kavin, E. Z. Gusakov, N. V. Sakharov
Publikováno v:
Technical Physics. 44:1054-1057
The main parameters and design of the Globus-M spherical tokamak are described, including the modifications introduced after construction was completed. The experimental program and possibilities for optimizing the operating regimes of the facility a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b468e0b1fd6de9941286054e06d4baf8
https://doi.org/10.1134/1.1259469
https://doi.org/10.1134/1.1259469
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