Zobrazeno 1 - 10
of 97
pro vyhledávání: '"N. Dolgetta"'
Autor:
M. Liao, N. Dolgetta, B. Lim, F. Simon, Y. Ilin, N. Mitchell, J. Reich, M. Lopez, A. Bonito Oliva, L. Wang, G. Shen
Publikováno v:
IEEE Transactions on Applied Superconductivity. 32:1-5
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a9996fc7f5d12426f878085db1e33c28
https://doi.org/10.1109/tasc.2022.3166128
https://doi.org/10.1109/tasc.2022.3166128
Akademický článek
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Autor:
N. Dolgetta, Thierry Schild, P. Garcia Sanchez, B. Levesy, J.C. Vallet, Enrique Gaxiola, C. Jong, Duke Hughes, Andrew Bruton, Travis Reagan, K. Freudenberg, I. Aviles, D. Hatfield, R. Okugawa, David H Vandergriff, W. Reiersen, Nicolai Martovetsky, D. Everitt, Paul Libeyre, Francois Nunio, D. Evans, Antony Mariani, Timothy L Chae, Stefano Sgobba, Neil Mitchell, C. Cormany, P. Decool, V. Bedakihale
Publikováno v:
Fusion Engineering and Design. 146:437-440
The Central Solenoid (CS), a key component of the ITER Magnet system, using a 45 kA Nb3Sn conductor, includes six identical coils, called modules, to form a solenoid, enclosed inside a structure providing vertical pre-compression and mechanical suppo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2718df791c127c53dd8464d515234944
https://doi.org/10.1016/j.fusengdes.2018.12.086
https://doi.org/10.1016/j.fusengdes.2018.12.086
Autor:
Weiyue Wu, Turck Bernard, Jing Wei, S. A. E. Langeslag, Ignacio Aviles Santillana, Lin Wang, Stefano Sgobba, F. Simon, Paul Libeyre, N. Dolgetta, Yuri Ilyin
Publikováno v:
IEEE Transactions on Plasma Science. 46:3223-3228
The correction coils (CCs) are a system of 18 superconducting coils composed of top CCs, side CCs, and bottom CCs, and are required to correct asymmetries and reduce magnetic error fields detrimental to the plasma performance of the ITER machine. The
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::73d3886af62937cc3d1ae836673a4a96
https://doi.org/10.1109/tps.2018.2849592
https://doi.org/10.1109/tps.2018.2849592
Autor:
Byung Su Lim, Alexander Vostner, N. Dolgetta, Yuri Ilyin, Neil Mitchell, Hyungjun Kim, Sebastien Koczorowski, Andrei Baikalov, Chen-yu Gung, F. Simon, Paul Libeyre, Bernard Turck, Arnaud Devred, Cormany Carl, Kazuya Hamada, Qing Hua, Enrique Gaxiola
Publikováno v:
IEEE Transactions on Applied Superconductivity. 28:1-6
The superconducting coils of the ITER magnet system have hundreds of electrical lap joints interconnecting superconducting cables. The joints operate in a magnetic field of up to 4 T, field derivatives of 0.5 T/s, and currents up to 70 kA. The accept
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::707d539cedaa0fe06ab450bd10acf275
https://doi.org/10.1109/tasc.2017.2778102
https://doi.org/10.1109/tasc.2017.2778102
Autor:
C. Jong, D. M. McRae, W. Reiersen, J.P. Smith, Ignacio Aviles, Duke Hughes, Travis Reagan, R. Pearce, Enrique Gaxiola, Neil Mitchell, C. Lyraud, Paul Libeyre, Nicolai Martovetsky, S. Litherland, N. Dolgetta, D. Hatfield, D. Evans, J. Y. Journeaux, K. Freudenberg, C. Cormany, Timothy L Chae, Robert Walsh, Stefano Sgobba, D. Everitt, S. A. E. Langeslag
Publikováno v:
IEEE Transactions on Applied Superconductivity. 28:1-5
The ITER central solenoid (CS) components are currently being manufactured. This Nb3Sn superconducting magnet will provide the magnetic flux swing required to induce up to 15 MA as plasma current. It includes six identical coils, called modules, stac
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e9791af16885117c55b43702cc74e4a6
https://doi.org/10.1109/tasc.2017.2775581
https://doi.org/10.1109/tasc.2017.2775581
Autor:
P. Libeyre, C. Cormany, N. Dolgetta, E. Gaxiola, Y. Ilyin, N. Mitchell, F. Simon, D. Evans, S. Sgobba, S.A.E. Langeslag, E. Niu, J. Wei, L. Wang, X. Dong, X. Yu, J. Xin, L. Liu, C. Li, C. Fang, W. Zheng
Publikováno v:
IEEE Transactions on Applied Superconductivity. 27:1-5
The system of correction coils (CC) is a component of the ITER magnet system, required to correct toroidal asymmetries and reduce error magnetic fields detrimental for physical processes in the plasma. It includes 18 coils, inserted in between toroid
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a746d3a14769de76d61d3eebbd848aab
https://doi.org/10.1109/tasc.2016.2630728
https://doi.org/10.1109/tasc.2016.2630728
Autor:
D. Hatfield, R. Abbott, C. Jong, C. Cormany, D. Everitt, D. Evans, J.P. Smith, S. Litherland, W. Reiersen, Peter Rosenblad, S. A. E. Langeslag, Nicolai Martovetsky, Enrique Gaxiola, T. Nentwich, Paul Libeyre, Stefano Sgobba, L. Myatt, K. Rackers, C. Lyraud, J. Daubert, T. Vollmann, K. Freudenberg, Neil Mitchell, J. Y. Journeaux, C. Brazelton, N. Dolgetta
Publikováno v:
IEEE Transactions on Applied Superconductivity. 26:1-5
The central solenoid (CS) is a key component of the ITER magnet system to provide the magnetic flux swing required to drive induced plasma current up to 15 MA. The manufacture of its different subcomponents has now started, following completion of th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6137b8bb31b79bed9be70a99ad85408b
https://doi.org/10.1109/tasc.2016.2545104
https://doi.org/10.1109/tasc.2016.2545104
Autor:
W. Reiersen, Bernard Turck, Stefano Sgobba, Paul Libeyre, Jeff Spitzer, S. Litherland, Jing Wei, Neil Mitchell, N. Dolgetta, A. Laurenti, C. Jong, Lin Wang, Peter Rosenblad, H. Li, Chao Fang, C. Lyraud, J.P. Smith, K. Freudenberg, Xiaoyu Dong, Nicolai Martovetsky, Chao Li, Yu Xiaowu, D. Everitt
Publikováno v:
Fusion Engineering and Design. :1103-1108
The manufacturing line of the ITER Correction Coils (CC) at ASIPP in Hefei (China) was completed in 2013 and the manufacturing line of the ITER Central Solenoid (CS) modules is under installation at General Atomic premises in Poway (USA). In both cas
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::74a1c10d0be4d52420d2c58a7e67e73c
https://doi.org/10.1016/j.fusengdes.2015.05.046
https://doi.org/10.1016/j.fusengdes.2015.05.046
Autor:
Huapeng Wu, N. Dolgetta, Jijun Xin, Hekki Handroos, Chao Fang, Paul Libeyre, Yuntao Song, Antti Salminen, Jing Wei, H. Li
Publikováno v:
Fusion Engineering and Design. :1960-1963
The ITER correction coil (CC) case reinforces the winding packs against the electromagnetic loads, minimizes stresses and deformations to the winding pack. The cases are made of high strength and high toughness austenitic stainless steel (316LN) hot
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a644ab4cb8274169a257a76e9e0380d4
https://doi.org/10.1016/j.fusengdes.2015.06.074
https://doi.org/10.1016/j.fusengdes.2015.06.074