Zobrazeno 1 - 10
of 71
pro vyhledávání: '"S. Sadakov"'
Autor:
L. Maqueda, J. Almenara, D. Piñeiro, E. Rodríguez, F. Rueda, A. Yáñez, F. Villone, M. Baldrís, I. Herrero, M.A. Serrano, S. Bender, D. Iglesias, D. Nikolaeva, S. Sadakov
Publikováno v:
Fusion Engineering and Design. 188:113435
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9cc6e7f3fc885c3748bf1e1eaec72663
https://doi.org/10.1016/j.fusengdes.2023.113435
https://doi.org/10.1016/j.fusengdes.2023.113435
Akademický článek
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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.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. :1601-1604
As any tokamak, ITER will operate with rather high magnetic fields. Quasi-static toroidal field inside of the vacuum vessel reaches ∼9 T and slow transient poloidal field ∼2.5 T. In a case of plasma vertical drift and disruption, characteristic t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b647e5b77e4d80f329508e9f2bc33c17
https://doi.org/10.1016/j.fusengdes.2015.06.023
https://doi.org/10.1016/j.fusengdes.2015.06.023
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
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Autor:
Ph. Chappuis, S. Sadakov, Mario Merola, A. Furmanek, F. Zacchia, Duck-Hoi Kim, Georges Dellopoulos, E. Daly, R. Mitteau, P. Heitzenroeder, E. Polunovski, A. Labusov, Zhang Fu, Chen Jiming, S. Khomiakov, M.A. Ulrickson, M. Kalish, S. Gicquel, R. Raffray, A. Martin, Michael Loughlin, A. Loarte, B. Calcagno
Publikováno v:
Fusion Engineering and Design. 88:1955-1959
The ITER in-vessel components have experienced a major redesign since the ITER Design Review of 2007. A set of in-vessel vertical stabilization (VS) coils and a set of in-vessel Edge Localized Mode (ELM) control coils have been implemented. The blank
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::416cd3cf5534d6b9b70bf8af28ac0dc6
https://doi.org/10.1016/j.fusengdes.2013.01.004
https://doi.org/10.1016/j.fusengdes.2013.01.004
Autor:
S. Sadakov, G. Dellopoulos, Ph. Chappuis, A. Zhmakin, V. Kolganov, M.A. Ulrickson, B. Calcagno, I. Poddubnyi, S. Khomiakov, J.J. Raharijaona, R. Raffray, Mario Merola
Publikováno v:
Fusion Engineering and Design. 88:1853-1857
Main function of the ITER blanket system [1] , [2] , [3] is to shield the vacuum vessel (VV) from nuclear radiation and thermal energy coming from the plasma. Blanket system consists of discrete blanket modules (BM). Each BM is composed of a first wa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::aab70feadf497b6964bda47375cf6caf
https://doi.org/10.1016/j.fusengdes.2013.03.031
https://doi.org/10.1016/j.fusengdes.2013.03.031
Autor:
Fu Zhang, A. Martin, D. Loesser, L. Ferrand, V. Rozov, V.R. Barabash, J. Palmer, L. Giancarli, S. Sadakov, R. Raffray, A. Furmanek, C.S. Kim, P. Chappuis, David Campbell, V. Komarov, Masataka Nakahira, D. Yao, A. Loarte, Mario Merola, R.A. Pitts, B. Calcagno, T. Hirai, Frederic Escourbiac, S. Gicquel, A.S. Kukushkin, Masayoshi Sugihara, R. Eaton, T. Jokinen, S. Mori, R. Mitteau
Publikováno v:
Fusion Engineering and Design. 85:2312-2322
The ITER plasma-facing components directly face the thermonuclear plasma and include the divertor, the blanket and the test blanket modules with their corresponding frames. The divertor is located at the bottom of the plasma chamber and is aimed at e
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4bbe7bb42b79fd30de205007b183ede1
https://doi.org/10.1016/j.fusengdes.2010.09.013
https://doi.org/10.1016/j.fusengdes.2010.09.013
Publikováno v:
Fusion Science and Technology. 56:134-138
Diagnostic plug for the ITER core charge exchange recombination spectroscopy (core CXRS) is located in the upper port 3. It transfers the light emitted by interaction of plasma ions with the diagnostic neutral beam (DNB). Conceptual design study of t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cfdb22dff9839c5dda3151f8be1f131e
https://doi.org/10.13182/fst09-a8890
https://doi.org/10.13182/fst09-a8890