Zobrazeno 1 - 10
of 32
pro vyhledávání: '"C. Vacas"'
Autor:
N. Casal, T. Giacomin, Javier Ordieres, Michael Walsh, Laura García-Ruesgas, C. Vacas, Jorge Roces, J. Fano, E. Rodríguez, J. Guirao, Silvia Iglesias, M. Gonzalez, Victor Udintsev
Publikováno v:
Fusion Engineering and Design. 123:793-796
During the final design review of Diagnostic Port Plugs, it has been highlighted that the current system of fixation, based on gaps, while it is not harmful for the port plug, it throws large uncertainties over the alignment of the optical systems pl
Autor:
Marcos Panizo, Dennis Ronden, Javier Ordieres, Spencer Pitcher, Russell Feder, P. Maquet, C. Vacas, Silvia Iglesias, Alejandro Suarez, Victor Udintsev, Victor Tanchuk, D. Loesser, Yuhu Zhai, J. Guirao, M. Kalish, Fabien Josseaume, M. Proust, Arkady Serikov, Michael Walsh, M. Portales, S. Pak, T. Giacomin
Publikováno v:
Fusion Engineering and Design, 102, 21-27
The generic upper port plug (GUPP) structure in ITER is a 6 m long metal box which deploys diagnostic components into the vacuum vessel. This structure is commonly used for all the diagnostic upper ports. The final design of the GUPP structure, which
Autor:
P. Maquet, Jorge Roces, C. Vacas, Silvia Iglesias, Victor Udintsev, J. Guirao, E. Rodríguez, S. Pak
Publikováno v:
Fusion Engineering and Design. :1492-1495
This paper demonstrates structural integrity of the first confinement boundary in Generic Upper Port Plug structures against cracking during service. This constitutes part of the justification to demonstrate that the non-aggression to the confinement
Autor:
P. Maquet, M. Smith, Javier Ordieres, J. Guirao, D. Delhom, C. Vacas, Victor Udintsev, T. Jourdan, T. Giacomin, Michael Walsh, Silvia Iglesias, Yuhu Zhai, S. Pak, D. Loesser, J. M. Drevon, M. Proust
Publikováno v:
Fusion Engineering and Design. :1488-1491
Due to this position close to the plasma, the port plug structure and the diagnostic first wall (DFW) contain water to allow cooling during operation and for heating during bake-out. To remove the heat coming from the plasma due to radiation and neut
Autor:
V.S. Udintsev, P. Maquet, E. Alexandrov, N. Casal, D. Cuenca, J.-M. Drevon, R. Feder, J.P. Friconneau, T. Giacomin, J. Guirao, S. Iglesias, F. Josseaume, B. Levesy, D. Loesser, J. Ordieres, E. Quinn, S. Pak, C. Penot, C.S. Pitcher, M. Portalès, M. Proust, A. Suarez, F. Seyvet, V. Tanchuk, Y. Utin, C. Vacas, C. Vasseur, M.J. Walsh
Publikováno v:
Fusion Engineering and Design. :993-997
Autor:
Victor Udintsev, C. Vacas, Jorge Roces, N. Casal, Silvia Iglesias, E. Rodríguez, S. Pak, J. Guirao, P. Maquet
Publikováno v:
Fusion Engineering and Design. :1652-1655
The purpose of this paper is present an overview of the methodology followed to calculate the dynamic amplification factors applied to the electromagnetic loads acting in the ITER generic port plugs. The methodology used for combining an EM transient
Autor:
Michael Walsh, R. Walton, I. Duran, C. Vacas, P. Gitton, J. Guirao, Slavomir Entler, Q. Pascual, M. Gonzalez, Silvia Iglesias, J. M. Carmona, M. Kocan, G. Sandford, George Vayakis
Publikováno v:
Fusion Engineering and Design.
The outer vessel steady-state sensors (OVSS) – a subsystem of the ITER magnetic diagnostics – will contribute to the measurement of the plasma current, plasma-wall clearance, and local perturbations of the magnetic flux surfaces near the wall. Th
Autor:
Y. Ma, M. Keane, Richard O’Connor, S. Simrock, Victor Udintsev, M. De Bock, C. Vorpah, Philip Andrew, N. Casal, Alexander Zvonkov, Michael Walsh, R. Feder, P. Stott, J. Govindrajan, M. von Hellermann, P. Gitton, M. Dapena, K. Okayama, Kiyoshi Itami, R. Gianella, R. Bouhamou, L. Caplat, T. Giacomin, G. Counsell, I. Keuhn, A. Martin, Y. Utin, P.T. Thomas, S. Pak, B. Levesy, E. Veshchev, J. Reich, C.S. Pitcher, D. Johnson, H.G. Lee, C. Watts, T. Fang, J. M. Drevon, Robin Barnsley, G. Vayakis, Vinay Kumar, Chris Walker, J. Guirao, Luciano Bertalot, P. Maquet, R. Reichle, Chris K. Orimoto, C. Vacas, A. Sirinelli
Publikováno v:
2015 IEEE 26th Symposium on Fusion Engineering (SOFE).
Diagnostics play a very important role in the modern Tokamak where optimum performance is essential. To achieve this, the device must be equipped with reliable and robust sensors and instrumentation that allow the operation envelope to be fully explo
Autor:
Alejandro Suarez, Victor Udintsev, Silvia Iglesias, C. Vacas, Michael Walsh, T. Giacomin, Eddie McCarron, Luciano Bertalot, Y. Utin, Sin-iti Kitazawa, Jack Sky, Philip Duckworth, Jean Marc Drevon, A. Martin, Fernando Mota, N. Casal, M. Portales, J. Guirao, Hao Cheng, Alexander Zvonkov, M.M. Kochergin, A.N. Mokeev, Christophe Penot
Publikováno v:
Fusion Engineering and Design, ISSN 0920-3796, 2015-10, Vol. 96-97, No. null
Archivo Digital UPM
Universidad Politécnica de Madrid
Archivo Digital UPM
Universidad Politécnica de Madrid
All around the ITER vacuum vessel, forty-four ports will provide access to the vacuum vessel for remote handling operations, diagnostic systems, heating, and vacuum systems: 18 upper ports, 17 equatorial ports, and 9 lower ports. Among the lower port
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::492448d9091969c00f4214137168574e
https://oa.upm.es/38725/
https://oa.upm.es/38725/