Zobrazeno 1 - 10
of 83
pro vyhledávání: '"B. Bellesia"'
Autor:
T. Hemmi, B. Bellesia, S. Hasegawa, P. Aprili, A. Bonito Oliva, E. Boter, M. P. Casas, M. Cornelis, K. Gomikawa, R. Harrison, A. Hernandez, M. Iguchi, T. Isono, M. Jimenez, H. Kajitani, S. Koczorowski, N. Koizumi, A. Lo Bue, K. Matsui, M. Nakahira, M. Nakamoto, K. Saito, K. Sakamoto, T. Sakurai, T. Shimizu, T. Suwa, K. Takano, K. Takebayashi, N. Tanaka, F. Tsutsumi, Y. Uno, E. Viladiu
Publikováno v:
Nuclear Fusion, Vol 64, Iss 6, p 066010 (2024)
In 2023, the manufacturing of all the ITER TF coils has been completed 15 years after the sign of procurement arrangements in 2008. This paper has been jointly submitted by F4E and QST to recollect the lessons learnt in the production of the two part
Externí odkaz:
https://doaj.org/article/77f591b6c5154272bf009b19cb44ec04
Akademický článek
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Akademický článek
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Akademický článek
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Publikováno v:
IEEE Transactions on Applied Superconductivity. 30:1-5
The ITER reactor relies in magnetic confinement of hot plasma. The main driver for the confinement is played by the Toroidal Field Coils. These magnets are composed by a Winding Pack, made of Nb3Sn superconductors, and a surrounding stainless steel s
Autor:
Edoardo Pompa, E. Viladiu, Juan Carlos Guerra García, Alessandro Bonito Oliva, E. Theisen, Eduard Pozuelo, Angela Hernandez, Marc Jimenez, Lionel Poncet, Andrei Calin, Paulo Figueiredo, Sebastien Koczorowski, Maria Paz Casas, P. Barbero, Narcis Pellicer, K. Libens, Charalampos Kosptopoulos, Alessandro Lo Bue, B. Bellesia, Piergiorgio Aprili, M. Cornelis, E. Boter, Cesar Luongo, R. Harrison
Publikováno v:
IEEE Transactions on Applied Superconductivity. 30:1-5
The plasma confinement of the International Tokamak Experimental Reactor (ITER) is provided by the magnetic field generated by 18 toroidal field coils. Fusion for Energy (F4E), the European Domestic Agency for ITER, is responsible for the supply of 1
Autor:
Eva Boter Rebollo, Marc Jimenez, Pierlugi Valente, Alessandro Lo Bue, B. Bellesia, Daniel Rossi, M. Cornelis, E. Viladiu, Cesar Luongo, P. Readman, L. Poncet, T. Boutboul, Piergiorgio Aprili, Valerie Casarin, Monica Martinez, Angela Hernandez, C. Sborchia, Maria Paz Casas Lino, Ander Loizaga, Pierre Gavouyere-Lasserre, Charalampos Kostopoulos, Rita Batista, Alessandro Bonito Oliva, Sebastien Koczorowski, Gennaro Romano, Byung Su Lim, Neil Mitchell, Edoardo Pompa, Pedro Carvas de Sousa, R. Harrison, Eduard Pozuelo-Segura
Publikováno v:
IEEE Transactions on Applied Superconductivity. 30:1-13
The plasma confinement of the International Tokamak Experimental Rector (ITER) is provided by the magnetic field generated by 18 toroidal field (TF) coils while 6 poloidal field (PF) and 6 central solenoid coils have the function to drive, shape and
Autor:
Marc Jimenez, Eva Boter Rebollo, Santiago Tarrago, Narcis Pellicer Sabadi, Oriano Dormicchi, Angela Hernandez Sanchez, B. Bellesia, L. Poncet, Stefano Pittaluga, Piergiorgio Aprili, Paz Casas Lino, M. Cornelis, P. Barbero, Jacques Silva Ribeiro, Eduard Viladiu Martinez, Michele Damone, Andres Felipe, K. Libens, R. Harrison, Jordi Cornella Medrano, Charalampos Kostopoulos, A. Bonito-Oliva
Publikováno v:
IEEE Transactions on Applied Superconductivity. 28:1-5
The magnetic field, necessary for the plasma confinement in the International Thermonuclear Experimental Reactor (ITER), Cadarache, France, is provided by the 18 Toroidal Field Coils (TFC). In each coil, this magnetic field is produced by circulating
Autor:
Angela Hernandez, P. Barbero, B. Bellesia, Charalampos Kostopoulos, Marc Jimenez, A. Bonito Oliva, E. Viladiu, Piergiorgio Aprili, M. Cornelis, O. Malpica, M. Spagnolo, L. Poncet, E. Boter, Narcis Pellicer, A. LoBue, R. Harrison, J. Cornella, S. Heikkinen, Pedro R. Figueroa Casas, K. Libens, M. Bolla, R. Batista, G. Falcitelli, E. Barbero, G. Veredas, R. Francone, M. Damone
Publikováno v:
IEEE Transactions on Applied Superconductivity. 28:1-5
The first European superconducting winding pack (WP) and the first set of coil cases [toroidal field coil cases (TFCC)] for ITER are going to be delivered in 2017. The TFCC are steel structures that provide structural integrity to the WP, contribute
Autor:
M. Cornelis, Neil Mitchell, R. Batista, J. Silva Ribeiro, K. Libens, Marc Jimenez, R. Francone, Sebastien Koczorowski, E. Boter Robello, Arnaud Devred, J. Caballero, E. Thyssen, N. Valle, O. Dormicchi, R. Harrison, A. Bonito-Oliva, J. Lucas, L. Poncet, Charalampos Kostopoulos, A. Felipe, P. Barbero, M. Casas Lino, E. Barbero Soto, A. Moreno, S. Tarrago, E. Viladu, J. Cornella, B. Bellesia, Narcis Pellicer, Piergiorgio Aprili, O. Malpica, M. Damone
Publikováno v:
IEEE Transactions on Applied Superconductivity. 28:1-5
The International Thermonuclear Experimental Reactor (ITER) magnetic system includes 18 toroidal field (TF) coils constructed using Nb3Sn cable-in-conduit superconductor. Each TF coil comprises a winding pack (WP) composed of seven double pancake mod