Zobrazeno 1 - 10
of 26
pro vyhledávání: '"D. Lousteau"'
Autor:
D. Loesser, R. Raffray, A. Cardella, A. Lodato, L. Bruno, T. Kodama, N. Miki, Yamada Masao, K. Ioki, K. Mohri, M. Hechler, F. Elio, D. Lousteau
Publikováno v:
Fusion Technology. 34:384-389
The ITER blanket system removes the surface heat flux from the plasma and from bulk heating by the neutrons, reduces the activity in the vacuum vessel (W) structural material to the level allowable...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34daa1abd7f8d8161485e1118e263497
https://doi.org/10.13182/fst98-a11963644
https://doi.org/10.13182/fst98-a11963644
Autor:
G. Johnson, K. Ioki, D. Lousteau, R. Parker, A. Cardella, G. Janeschitz, R. Tivey, F. Elio, Masanori Onozuka, G. Kalinin, V.R. Barabash, Yousry Gohar, G. Sannazzaro
Publikováno v:
Journal of Nuclear Materials. :74-84
Design and R&D have progressed on the ITER vacuum vessel, shielding and breeding blankets, and the divertor. The principal materials have been selected and the fabrication methods selected for most of the components based on design and R&D results. T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::856e5481415c86437710971880999dbb
https://doi.org/10.1016/s0022-3115(98)00356-0
https://doi.org/10.1016/s0022-3115(98)00356-0
Autor:
R. Raffray, E. Zolti, D. Lousteau, K. Ioki, K. Mohri, A. Cardella, L. Bruno, R. Parker, N Tachikawa
Publikováno v:
Physica Scripta. :53-59
The First Wall (FW) is one of the key components of the International Thermonuclear Experimental Reactor (ITER). It must be designed to remove the surface heat flux from the plasma, while, in combination with a structurally integral shield, reduce th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cadc52521a89f1d8a8c9de20e1592c3e
https://doi.org/10.1088/0031-8949/1996/t64/008
https://doi.org/10.1088/0031-8949/1996/t64/008
Publikováno v:
Fusion Engineering and Design. 16:205-215
The Assembly and Maintenance (AM however, their use shall be limited to less frequent or unplanned operations such as the change-out of internal shielding or blankets.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f8fd63a2a49ba686bff2173b4633fcfd
https://doi.org/10.1016/0920-3796(91)90194-u
https://doi.org/10.1016/0920-3796(91)90194-u
Autor:
F.C. Davis, P.L. Goranson, B.E. Nelson, D. Lousteau, D.L. Conner, John D Galambos, D. Williamson
Publikováno v:
15th IEEE/NPSS Symposium. Fusion Engineering.
An analytic parametric scoping tool has been developed for application to first wall (FW) design problems. Both thermal and disruption force effects are considered. For the high heat flux and high disruption load conditions expected in the Internatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c4b0403c1beea1628a89abd9a997eafb
https://doi.org/10.1109/fusion.1993.518532
https://doi.org/10.1109/fusion.1993.518532
Autor:
D. Lousteau, B.E. Nelson, H. Attaya, Laila El-Guebaly, Saurin Majumdar, C. Johnson, Richard F. Mattas, Mohamed A. Abdou, Alice Ying, J. Kopasz, Mohamed E. Sawan, A. Badawi, Yousry Gohar, D.L. Smith, Michael C. Billone, E. A. Mogahed, D. Williamson, I.N. Sviatoslavsky, Gerald L. Kulcinski, A.R. Raffray
Publikováno v:
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering.
The impact of the HARD (high aspect ratio design) option on the blanket and shield performance as concluded from CDA (conceptual design activity) is examined. The neutron wall load distributions were calculated for the different operating modes of HA
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9346c799ded83d8917e449890d4adde7
https://doi.org/10.1109/fusion.1991.218672
https://doi.org/10.1109/fusion.1991.218672
Publikováno v:
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering.
During the conceptual design activity (CDA) for the International Thermonuclear Experimental Reactor (ITER), a reactor design was established that emphasized performance of the individual systems in a minimum overall reactor size. The resulting high
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e5b30bc52ccf3abf34d2554e4230fe9f
https://doi.org/10.1109/fusion.1991.218684
https://doi.org/10.1109/fusion.1991.218684
Autor:
L. Bruno, R. Parker, A. Cardella, D. Lousteau, K. Ioki, K. Mohri, Hideyuki Takatsu, F. Elio, N. Miki, Yousry Gohar, D. Loesser, Richard F. Mattas, M. Hechler, Yamada Masao, W. Daenner, R. Raffray, T. Kodama, D. Williamson, A. Lodato, Yu.S. Strebkov
Publikováno v:
17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131).
Significant improvements of the ITER blanket were possible with the better definition of the thermal and electromagnetic effects. A supporting double wall backplate with reinforcement about the ports has been defined. The module has been simplified a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2bf5007d70d4723c6e98993d32f6360c
https://doi.org/10.1109/fusion.1997.687790
https://doi.org/10.1109/fusion.1997.687790
Autor:
Y. Strebkov, E. Zolti, R. Mattas, P. Lorenzetto, K. Ioki, R. Raffray, T. Kuroda, K. Mohri, Michael C. Billone, Y. Gohar, A. Cardella, W. Dänner, S. Majumdar, Hideyuki Takatsu, D. Lousteau
Publikováno v:
Proceedings of 16th International Symposium on Fusion Engineering.
A breeding blanket design has been developed for ITER to provide the necessary tritium fuel to achieve the technical objectives of the Enhanced Performance Phase. It uses a ceramic breeder and water coolant for compatibility with the ITER machine des
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::40ecfcfac794bc3ba777bb85eea1fb18
https://doi.org/10.1109/fusion.1995.534253
https://doi.org/10.1109/fusion.1995.534253
Autor:
K. Shimizu, R. Parker, E. Zolti, N. Tachakawa, G. Kalinin, D. Williamson, D. Lousteau, A. Cardella, R. T. Santoro, F. Elio, T. Takahashi, K. Ioki, T. Iizuka, K. Mohri, Y. Gohar, R. Raffray, G. Johnson
Publikováno v:
Proceedings of 16th International Symposium on Fusion Engineering.
The Vacuum Vessel is part of the Tokamak-Basic Machine and provides the primary high vacuum and tritium boundary for the plasma. The vessel is also a major safety barrier and must support electromagnetic loads during plasma disruptions and vertical d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e854636c6f78f15b9c145a96635910c2
https://doi.org/10.1109/fusion.1995.534192
https://doi.org/10.1109/fusion.1995.534192