Zobrazeno 1 - 10
of 152
pro vyhledávání: '"R. Raffray"'
Autor:
T. Hirai, L. Bao, V. Barabash, R. Carrat, Ph. Chappuis, R. Eaton, P. Edwards, F. Escourbiac, S. Gicquel, V. Komarov, M. Merola, R. Raffray, J. Chen, K. Wang, A. Gervash, A. Makhankov, N. Arkhipov, V. Safronov
Publikováno v:
Fusion Engineering and Design. 189:113454
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::32cfd5f2ed4e7dffed9f4b3a4c0b382b
https://doi.org/10.1016/j.fusengdes.2023.113454
https://doi.org/10.1016/j.fusengdes.2023.113454
Autor:
T. Hirai, L. Bao, V. Barabash, Ph. Chappuis, R. Eaton, F. Escourbiac, M. Merola, R. Mitteau, R. Raffray, J. Linke, Th. Loewenhoff, D. Dorow-Gerspach, G. Pintsuk, M. Wirtz, D. Boomstra, C.J. Klaassen, A. Magielsen, J. Chen, P. Wang
Publikováno v:
Fusion Engineering and Design. 186:113338
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d2465a341ce231783565b0ac05ef5846
https://doi.org/10.1016/j.fusengdes.2022.113338
https://doi.org/10.1016/j.fusengdes.2022.113338
China’s technological achievements on ITER enhanced heat flux first wall in the pre-PA qualification
Autor:
R. Raffray, Delong Luo, Liman Bao, Jing Zhao, Chuanhong Pan, V.R. Barabash, Jian Sun, Chen Jiming, Zhanhong Wang, Tongzhen Fang, Wang Kun, Xiang Liu, Wang Pinghuai, Erwu Niu
Publikováno v:
Fusion Engineering and Design. 146:2045-2048
The Chinese Domestic Agency (DA) is procuring ITER Enhanced Heat Flux (EHF) First Wall (FW) panels which shall withstand a surface heat load up to 4.7 MW/m2 during ITER operation. Prior to the implementation of the ITER Procurement Arrangement (PA),
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::95d34265e83b89e4083a8b51b70161ef
https://doi.org/10.1016/j.fusengdes.2019.03.098
https://doi.org/10.1016/j.fusengdes.2019.03.098
Publikováno v:
Fusion Engineering and Design
Remote maintenance in fusion machines such as JET (Joint European Torus) and ITER (International Thermonuclear Experimental Reactor) relies on sliding interfaces such as bolted joints. Experience in JET, where removal torques much higher than install
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c431c377b038f47ec7d6e9e10a307097
https://doi.org/10.1016/j.fusengdes.2018.12.064
https://doi.org/10.1016/j.fusengdes.2018.12.064
Autor:
R. Raffray, S.N. Tomilov, V.M. Safronov, E.V. Parshutin, M.N. Sviridenko, Y. Strebkov, A. Leshukov, S. Gicquel, I. Poddubnyi, R. Eaton
Publikováno v:
Fusion Engineering and Design. 146:1963-1966
JSC NIKIET is a main supplier of ITER in-vessel components and its responsibility includes the manufacture of the FW beam, finger bodies, and the mechanical attachment system of the Enhanced Heat Flux (EHF) First Wall (FW) Panels in the framework of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::22d9f03c65e06c84b19ed74f4b490a72
https://doi.org/10.1016/j.fusengdes.2019.03.076
https://doi.org/10.1016/j.fusengdes.2019.03.076
Autor:
P.Y. Piskarev, R. Raffray, O. N. Sevryukov, V.M. Safronov, I.V. Mazul, V. Kuznetsov, T.М. Guryeva, Ogursky, D. Glazunov, R. Eaton, A. Gervash, R. Giniyatulin
Publikováno v:
Fusion Engineering and Design. 146:2292-2296
The article describes the method of vacuum induction brazing of beryllium tiles covering the surface of the first wall of ITER. To prevent the formation of brittle intermetallic and preservation of the mechanical properties of the CuCrZr alloy, it le
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::00f60b3968bd0ab4a90e0850fbb51120
https://doi.org/10.1016/j.fusengdes.2019.03.175
https://doi.org/10.1016/j.fusengdes.2019.03.175
Autor:
A. Marin, P. Edwards, F. Lucca, B. Calcagno, F. Viganò, S. Gicquel, I. Pagani, C. Bertolini, R. Raffray
Publikováno v:
Fusion Engineering and Design. 146:1882-1885
A significant analysis effort was undertaken to address the challenging ITER Blanket Manifold [ 1 ] (BM) design requirements resulting from electromagnetic (EM) major disruptions and vertical displacements events in a very demanding neutronic environ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::59c21b79faf60f4cc381bde8fba8bfd6
https://doi.org/10.1016/j.fusengdes.2019.03.056
https://doi.org/10.1016/j.fusengdes.2019.03.056
Autor:
A. Leshukov, S.N. Tomilov, V.M. Safronov, I.V. Mazul, A. Gervash, B. Calcagno, M.N. Sviridenko, E. Okuneva, R. Eaton, S. Gicquel, R. Raffray
Publikováno v:
Fusion Engineering and Design. 146:2407-2411
A full-scale prototype of the first wall (FW) panel shall be manufactured in the framework of the Procurement Arrangement between IO ITER and Russian Domestic Agency signed on 13.02.2014 (Leshukov, 2016) [ 1 ]. The design of the full-scale prototype
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54997aa6b83b7edb8a30d39196549f41
https://doi.org/10.1016/j.fusengdes.2019.04.002
https://doi.org/10.1016/j.fusengdes.2019.04.002
Autor:
I.V. Danilov, A.V. Razmerov, Y. Strebkov, V. Kolganov, R. Eaton, E.V. Parshutin, S. Khomiakov, I. Poddubnyi, S. Timofeev, R.A. Tagiev, A. Malyshev, K. Egorov, V.M. Safronov, R. Raffray, M.N. Sviridenko, A. B. Putrik
Publikováno v:
Fusion Engineering and Design. 146:2474-2478
Insulated pads are used on ITER blanket module connectors and the first wall; their main insulating function is to break any current loop between the shield block and vacuum vessel and/or between the first wall panel and shield block. The design of t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8725f17489474135d2ecb97c5f5a9748
https://doi.org/10.1016/j.fusengdes.2019.04.022
https://doi.org/10.1016/j.fusengdes.2019.04.022
Autor:
P. Lorenzetto, Paul Marshall, Montse Felip, L. Guerrini, Mario Merola, A. Durocher, S. Heikkinen, L. Ferrand, Tindaro Cicero, B. Riccardi, Frederic Escourbiac, José Andrade, Georges Dellopoulos, P. Gavila, Stefano Banetta, R. Mitteau, S. Gicquel, R. Raffray
Publikováno v:
Fusion Engineering and Design. 136:975-982
Fusion for Energy (F4E), the European Domestic Agency for ITER, is responsible for a significant share of the overall procurement of internal components inside the vacuum vessel, the largest ones being as follows: (1) 48% of the ITER blanket first wa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5df90da9cf1b0aa8495fa194317b1240
https://doi.org/10.1016/j.fusengdes.2018.04.050
https://doi.org/10.1016/j.fusengdes.2018.04.050