Zobrazeno 1 - 10
of 129
pro vyhledávání: '"S, Chiocchio"'
Autor:
W. Shu, A. Dammann, J.G. van der Laan, R. Pascal, J.J. Cordier, David Campbell, J.M. Fourneron, S. Chiocchio, Mario Merola, Joëlle Elbez-Uzan, M. Iseli, A. Siarras, Iva Schneiderova, B. Levesy, Scott Willms, Byoung-Yoon Kim, D. Lazarov, M. Gasparotto, W. Ring, J.-C. Nevière, V.R. Barabash, Michael Loughlin, J.P. Friconneau, C.-Y. Jung, Joseph Snipes, G. Dell’Orco, L. Giancarli
Publikováno v:
Fusion Engineering and Design
The paper describes the organization of the Test Blanket Module (TBM) program, its overall objective and schedule and the status of the technical activities within the ITER Organization-Central Team (IO-CT). The latter include the design integration
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6dcf152389428fe7a89ac9de89e6cc63
https://doi.org/10.1016/j.fusengdes.2015.11.046
https://doi.org/10.1016/j.fusengdes.2015.11.046
Autor:
Sergio Orlandi, S. Chiocchio, Andreas Lee, Yasuhiro Iwata, G. Rigoni, Jean-Jacques Cordier, I. Kuehn, Miikka Kotamaki, Leontin Carafa, Romaric Darbour, Alain Baudry, Thomas Jeannoutot, J. Reich, Rachel Packer, J.S. Bak, Joelle Elbez, Magali Benchikhoune, B. Levesy, Simon Sweeney, Laurent Patisson, Giovanni di Giuseppe
Publikováno v:
Fusion Engineering and Design. :240-243
The ITER Tokamak complex consists of Tokamak, diagnostic and tritium buildings. The Tokamak machine is located in the bioshield pit of the Tokamak building. Plant systems are implemented in the three buildings and are strongly interfacing with the To
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::46cb537da5d00b74a27ebf66f5d30bde
https://doi.org/10.1016/j.fusengdes.2015.06.115
https://doi.org/10.1016/j.fusengdes.2015.06.115
Autor:
Laurent Schmieder, S. Chiocchio, I. Kuehn, Laurent Patisson, Thibault Tsedri, James Klingsmith, G. Rigoni, Miikka Kotamaki, Leontin Carafa, Jean-Jacques Cordier
Publikováno v:
Fusion Engineering and Design. 86:632-635
The ITER site consists of almost 30 buildings to service the Tokamak machine which is located in the centre of the Tokamak Complex facility with the Tokamak-, Diagnostic- and Tritium building. The design of a large part of the ITER plant systems will
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8e56e890dabdf863c81c586804f00552
https://doi.org/10.1016/j.fusengdes.2011.02.044
https://doi.org/10.1016/j.fusengdes.2011.02.044
Autor:
S. Chiocchio, D. Cox, Keishi Sakamoto, P. U. Lamalle, T. Gassmann, A. Tanga, G. Saibene, F. Kazarian, B. Beaumont, G. G. Denisov, Tullio Bonicelli, M. A. Henderson, C. Darbos, David A Rasmussen, Ujjwal Baruah, Aparajita Mukherjee, R. Sartori, H. Decamps
Publikováno v:
Fusion Engineering and Design. 85:1245-1249
The RF heating and current drive (H&CD) systems that are to be installed in ITER during the construction phase, are the electron cyclotron (EC) and ion cyclotron (IC) systems. They are complex assemblies of high voltage power supplies (HVPS), RF gene
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::10430598e032c1b7c6102723c69b7633
https://doi.org/10.1016/j.fusengdes.2010.03.013
https://doi.org/10.1016/j.fusengdes.2010.03.013
Autor:
S. Chiocchio, C. Roldan, C. Gordon, G. Saibene, L. Rodriguez Rodrigo, J.A. Carretero, Sergio Ciattaglia, Alfredo Portone, P. Barabaschi, Joëlle Uzan-Elbez, D. Hureau, J.Ph. Girard
Publikováno v:
Fusion Engineering and Design. 84:2059-2063
The operating limits and conditions (OLCs) are operating parameters and conditions, chosen among all system/components, which, together, define the domain of the safe operation of ITER in all foreseen ITER states (operation, maintenance, commissionin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9e180332e9ee5ae834e1ede639122ac7
https://doi.org/10.1016/j.fusengdes.2008.10.007
https://doi.org/10.1016/j.fusengdes.2008.10.007
Publikováno v:
Fusion Engineering and Design. 84:1584-1587
ITER has to focus on all processes that ensure the permanent consistency between the requirements of ITER and the performance attributes of its components. This includes integration tolerance studies. One of the main goals of this work is to establis
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4c5aa1a1aa24c924f20ad1367390f049
https://doi.org/10.1016/j.fusengdes.2009.01.012
https://doi.org/10.1016/j.fusengdes.2009.01.012
Publikováno v:
Fusion Engineering and Design. 82:548-554
The construction of ITER will represent a major challenge for the fusion community at large, because of the intrinsic complexity of the tokamak design, the large number of different systems which are all essential for its operation, the worldwide dis
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2cced275cf9f05052c6561bfdd182a84
https://doi.org/10.1016/j.fusengdes.2007.06.019
https://doi.org/10.1016/j.fusengdes.2007.06.019
Publikováno v:
2015 IEEE 26th Symposium on Fusion Engineering (SOFE).
The main idea of the presented approach consists in looking at ITER more as a global integrated system and less as a set of components. In addition to the “classical” progress indicators (design reviews, etc.), our approach introduces new indicat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::501406b9750609d6ee367cfb3f14343d
https://doi.org/10.1109/sofe.2015.7482279
https://doi.org/10.1109/sofe.2015.7482279
Autor:
M. Nakahira, W. Daenner, T. Kuroda, Yu. Utin, S. Maruyama, V.N. Tanchuk, S Kajiura, S. Chiocchio, Masato Akiba, P. Lorenzetto, N Miki, M. Morimoto, Masanori Onozuka, J Ohmori, G. Federici, P. Barabaschi, F. Elio, Kazuyoshi Sato, L. Jones, Mikio Enoeda, Y. Strebkov, V. Barabash, R. Tivey, Koichiro Ezato, Mario Merola, V. A. Krylov, A. Gervash, K. Ioki, S. Suzuki, V. Rozov, D. Grebennikov
Publikováno v:
Journal of Nuclear Materials. :31-38
Progress has been made in the preparation of the procurement specifications for key nuclear components of ITER. Detailed design of the vacuum vessel (VV) and in-vessel components is being performed to consider fabrication methods and non-destructive
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::67262c033d8a5e0cdc17a56cd3cb3473
https://doi.org/10.1016/j.jnucmat.2004.04.003
https://doi.org/10.1016/j.jnucmat.2004.04.003
Autor:
V. A. Krylov, S. Suzuki, Yamada Masao, M. Nakahira, R. Tivey, V.N. Tanchuk, E. Martin, K. Ioki, P. Lorenzetto, Mario Merola, Y. Strebkov, S. Chiocchio, A. Gervash, W. Daenner, V.R. Barabash, Yu. Utin, Mikio Enoeda, V. Rozov, F. Elio, P. Barabaschi, L. Jones, C. Ibbott, I.V. Mazul, T. Kuroda
Publikováno v:
Nuclear Fusion. 43:268-273
During the preparation of the procurement specifications of ITER for long lead-time items, several detailed vacuum vessel (VV) design improvements are being pursued, such as elimination of the inboard triangular support, adding a separate interspace
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f4feaab14a1275d95d1ce5d52e6a5d59
https://doi.org/10.1088/0029-5515/43/4/308
https://doi.org/10.1088/0029-5515/43/4/308