Zobrazeno 1 - 10
of 41
pro vyhledávání: '"A.N. Romannikov"'
Autor:
D. Van Eester, Riccardo Ragona, Yu. N. Dnestrovskii, Ye. O. Kazakov, A. M. Messiaen, A.V. Melnikov, P.P. Khvostenko, A.N. Romannikov, I.N. Roy, J. Ongena
Publikováno v:
Fusion Engineering and Design. 146:787-791
This paper describes a conceptual ICRH system for the tokamak T-15MД, in construction at the Nuclear Fusion Institute of the Kurchatov Research Centre for Atomic Energy in Moscow. The proposed system consists of a number of Travelling Wave Antenna s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::66aa15abe74f39ddf510cccc7b2bcd08
https://doi.org/10.1016/j.fusengdes.2019.01.080
https://doi.org/10.1016/j.fusengdes.2019.01.080
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
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Autor:
R. Raffray, I.V. Danilov, S. Khomiakov, D. Mitin, K. Egorov, S. Kirillov, K. Skladnov, A.N. Romannikov, V. Elkin, S. Sadakov, E.V. Parshutin, I. Poddubnyi, V. Kolganov, Ph. Chappuis, B. Calcagno, A. B. Putrik, Y. Strebkov
Publikováno v:
Fusion Engineering and Design. 124:516-521
In ITER blanket system, electrical connectors (“E–straps”, ES) are used to form a low impedance electrical path from shield blocks (SB) to the vacuum vessel (VV). Main functions of ES is providing current from SB to VV. ES shall withstand elect
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2aab96c27f317c71e9b83b5a08510fd
https://doi.org/10.1016/j.fusengdes.2017.05.014
https://doi.org/10.1016/j.fusengdes.2017.05.014
Autor:
A.V. Solopeko, N.V. Injutin, A.N. Romannikov, V. A. Belyakov, P.P. Khvostenko, E.N. Bondarchuk, I.O. Anashkin
Publikováno v:
Fusion Engineering and Design. 124:114-118
Presently, the Tokamak T-15MD is being built in NRC “Kurchatov Institute”, Russia. All elements of the magnet system have been manufactured by the end of 2015. The preassembly of the tokamak T-15MD magnet system is carried out at plant in Bryansk
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ba90b0e037ad9c5252d84aebf67c7dc7
https://doi.org/10.1016/j.fusengdes.2017.03.064
https://doi.org/10.1016/j.fusengdes.2017.03.064
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:
Yu. G. Dragunov, A.V. Razmerov, G.V. Dubinin, V.M. Safronov, V.Yu. Kolganov, P.D. Trofimovich, A. Zhmakin, A.N. Romannikov, A.Yu. Leshukov, S.E. Khomyakov, E.V. Parshutin, Y. Strebkov, K. Egorov, R. Eaton, V.A. Maksimov, A. Gervash, S.Yu. Kirillov, I.V. Mazul, V. A. Belyakov, M.N. Sviridenko, S.V. Makarov
Publikováno v:
Fusion Engineering and Design. :61-72
The two following ITER blanket-relevant Procurement Arrangements (PA) were signed by Russian Federation and ITER Organization in 2014: 1) 1.6.P1ARF.01 “Blanket First Wall” (signed on 14-th of February, 2014); 2) 1.6.P3.RF.01 “Blanket Module Con
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6289594a0684462400ae86739bdc9653
https://doi.org/10.1016/j.fusengdes.2016.03.052
https://doi.org/10.1016/j.fusengdes.2016.03.052
Autor:
Thierry Cerisier, Natalya Rosales, Jean-Jacques Cordier, Ekaterina Mironova, Yuri Rumyantsev, Alexis Dammann, Sergey Portone, Elena Mitrofanova, Victor Minakov, A.N. Romannikov, B. Levesy
Publikováno v:
Fusion Engineering and Design. :1153-1157
To achieve the overall ITER machine availability target, the availability of diagnostics and heating port plugs shall be as high as 99.5%. To fulfill this requirement, it is mandatory to test the port plugs at operating temperature before installatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d9b2e62e522c69f947c00adc491d68e9
https://doi.org/10.1016/j.fusengdes.2015.12.064
https://doi.org/10.1016/j.fusengdes.2015.12.064
Autor:
A.N. Romannikov, S. Sadakov, E.V. Parshutin, Ph. Chappuis, V. Kolganov, I.V. Danilov, S. Khomiakov, R. Raffray, Y. Strebkov, I. Poddubnyi, A. Cheburova, K. Skladnov, D. Vlasov, K. Egorov, B. Calcagno, R. Roccella, A. Zhmakin
Publikováno v:
Fusion Engineering and Design. :261-266
A standard ITER Blanket module (BM) is attached to the Vacuum Vessel (VV) with a special system of Blanket Module Connections (BMCs) comprising flexible supports, insulating key pads and electrical straps. BMCs fix the modules relative to the VV and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::20d2dbec1a461d6bdd9d63af11458ba9
https://doi.org/10.1016/j.fusengdes.2016.03.015
https://doi.org/10.1016/j.fusengdes.2016.03.015
Publikováno v:
Fusion Engineering and Design. :2182-2186
The port plug test facility (PPTF) in the ITER hot cell building (HCB) will be used to test activated equatorial port plugs (EPP). The design of the PPTF and the HCB walls adjacent to the PPTF aims to have the docking room, which is next to the test
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f237bba2692884e80aa3fe79a4f542a2
https://doi.org/10.1016/j.fusengdes.2015.02.005
https://doi.org/10.1016/j.fusengdes.2015.02.005