Zobrazeno 1 - 10
of 87
pro vyhledávání: '"S. Gicquel"'
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:
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:
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:
N. Mozzani, Mario Walter, L. Frank, E. Oñorbe, A. Ulbricht, M. Hernández-Mayoral, S. Gicquel, Denis Sornin, U. Ehrnstén, J. Rantala, Jarir Aktaa, Y. de Carlan, A. Hobt
Publikováno v:
Metallurgical and Materials Transactions A
Metallurgical and Materials Transactions A, Springer Verlag/ASM International, 2021, https://doi.org/10.1007/s11661-021-06327-0. ⟨10.1007/s11661-021-06327-0⟩
Metallurgical and Materials Transactions A 52(2021), 3541-3552
Metallurgical and Materials Transactions A, 2021, https://doi.org/10.1007/s11661-021-06327-0. ⟨10.1007/s11661-021-06327-0⟩
Sornin, D, Ehrnstén, U, Mozzani, N, Rantala, J, Walter, M, Hobt, A, Aktaa, J, Oñorbe, E, Hernandez-Mayoral, M, Ulbricht, A, Gicquel, S, Frank, L & de Carlan, Y 2021, ' Creep Properties of 9Cr and 14Cr ODS Tubes Tested by Inner Gas Pressure ', Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, vol. 52, pp. 3541-3552 . https://doi.org/10.1007/s11661-021-06327-0
Metallurgical and Materials Transactions A, Springer Verlag/ASM International, 2021, https://doi.org/10.1007/s11661-021-06327-0. ⟨10.1007/s11661-021-06327-0⟩
Metallurgical and Materials Transactions A 52(2021), 3541-3552
Metallurgical and Materials Transactions A, 2021, https://doi.org/10.1007/s11661-021-06327-0. ⟨10.1007/s11661-021-06327-0⟩
Sornin, D, Ehrnstén, U, Mozzani, N, Rantala, J, Walter, M, Hobt, A, Aktaa, J, Oñorbe, E, Hernandez-Mayoral, M, Ulbricht, A, Gicquel, S, Frank, L & de Carlan, Y 2021, ' Creep Properties of 9Cr and 14Cr ODS Tubes Tested by Inner Gas Pressure ', Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, vol. 52, pp. 3541-3552 . https://doi.org/10.1007/s11661-021-06327-0
International audience; Oxide-dispersion strengthened steels are promising materials for extreme service conditions including nuclear reactors core. In service conditions, nuclear fuel claddings are exposed to the fission gas pressure at temperatures
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c67edd0cd47649b0c2b29ef76732ed76
https://hal-cea.archives-ouvertes.fr/cea-03263217
https://hal-cea.archives-ouvertes.fr/cea-03263217
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
Akademický článek
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Autor:
C. Chaullier, Georges Dellopoulos, P. Edwards, S. Mori, B. Calcagno, A. Martin, S. Gicquel, P. Chappuis, M. Norman, R. Raffray, Chang-Hwan Choi
Publikováno v:
Fusion Engineering and Design. 124:328-332
The Final Design Review for the Blanket Manifold (MA) was successfully held in December 2015. A concerted effort has been necessary to finalise the multi-pipe design, verification by analysis and practical validation to address challenging design req
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::40ba71408ff6348457b5ad4a953604b7
https://doi.org/10.1016/j.fusengdes.2017.03.110
https://doi.org/10.1016/j.fusengdes.2017.03.110
Autor:
A. Gervash, B. Calcagno, M.N. Sviridenko, A. Leshukov, S.N. Tomilov, Y. Strebkov, R. Eaton, M. Khokhlov, R. Raffray, S. Gicquel, V.M. Safronov, E. Okuneva
Publikováno v:
Fusion Engineering and Design. 158:111897
The First Wall (FW) is a component of the Blanket System facing the plasma. Two types of FW panel design have been developed based on the design heat flux: the Enhanced Heat Flux First Wall (EHF FW) panels designed for a 4.7 MW/m2 heat flux, and the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::43b43f4448055ce922f74af618e77e0c
https://doi.org/10.1016/j.fusengdes.2020.111897
https://doi.org/10.1016/j.fusengdes.2020.111897
Autor:
R. Raffray, S. Gicquel, V.M. Safronov, E. Okuneva, B. Calcagno, M.N. Sviridenko, R. Eaton, S. Kozlov, S.N. Tomilov, A. Leshukov
Publikováno v:
Fusion Engineering and Design. 158:111844
The internal surface of the vacuum vessel of ITER is covered with 440 Blanket Modules (BM). Each BM consists of the First Wall (FW) panel and the Shield Block (SB). JSC NIKIET and JSC NIIEFA are responsible for manufacturing and procurement of the FW
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::70ed6ab841fb94dba06fa94650fd399f
https://doi.org/10.1016/j.fusengdes.2020.111844
https://doi.org/10.1016/j.fusengdes.2020.111844