Zobrazeno 1 - 10
of 150
pro vyhledávání: '"B. LEVESY"'
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:
J. Guirao, Blaise Hovine, B. Levesy, Bernard Cuquel, Jean-Jacques Cordier, Fabien Josseaume, J.P. Martins, Yannick Le Tonqueze
Publikováno v:
Fusion Engineering and Design. 136:902-907
The Port Plug handling system aims to insert and remove the ITER Port Plugs installed at the Equatorial and Upper levels of the ITER Tokamak. As the Port Plugs activation and contamination levels prevent hands-on access, their safe transfer is ensure
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::744239361ffca0d052dd9907917b4a06
https://doi.org/10.1016/j.fusengdes.2018.04.033
https://doi.org/10.1016/j.fusengdes.2018.04.033
Autor:
B. Levesy, A. Antipenkov, Davide Flammini, Rosaria Villari, Michael Loughlin, M. Dremel, Dan Gabriel Cepraga, Luigino Petrizzi, Fabio Moro, Gilio Cambi, Salvatore Podda
Publikováno v:
Fusion Engineering and Design. :461-467
The ITER main vacuum system consists of six torus exhaust pumps integrated in the Cryostat through dedicated housings at the building B1 level. The Port Cell area outside the cryopump plug is affected by neutrons streaming through the housing structu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::259244689071482eea954e107f0ecc07
https://doi.org/10.1016/j.fusengdes.2016.02.081
https://doi.org/10.1016/j.fusengdes.2016.02.081
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:
Thierry Cerisier, Natalya Rosales, Jean-Jacques Cordier, Ekaterina Mironova, Yuri Rumyantsev, Alexis Dammann, Sergey Portone, Elena Mitrofanova, Victor Minakov, A.N. Romannikov, B. Levesy
Publikováno v:
Fusion Engineering and Design. :1153-1157
To achieve the overall ITER machine availability target, the availability of diagnostics and heating port plugs shall be as high as 99.5%. To fulfill this requirement, it is mandatory to test the port plugs at operating temperature before installatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d9b2e62e522c69f947c00adc491d68e9
https://doi.org/10.1016/j.fusengdes.2015.12.064
https://doi.org/10.1016/j.fusengdes.2015.12.064
Publikováno v:
Fusion Engineering and Design. 100:501-506
Shutdown dose rates for planned maintenance purposes is an active research field in ITER. In this work the radiation (neutron and gamma) cross-talk between ports in the most conservative case foreseen in ITER is investigated: the presence of a torus
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::eb02bd39a9927fd0d56c3896ab888baf
https://doi.org/10.1016/j.fusengdes.2015.07.027
https://doi.org/10.1016/j.fusengdes.2015.07.027
Autor:
L. Meunier, Dieter Leichtle, B. Levesy, M. Shannon, R. Sartori, P. U. Lamalle, E. Polunovskiy, Andrew Turner
Publikováno v:
Fusion Engineering and Design. :357-360
The Ion Cyclotron Heating and Current Drive (ICH&CD) system will reside in ITER equatorial port plugs 13 and 15. Shutdown dose rates (SDDR) within the port interspace are required to be less than 100 μSv/h at 10 6 s cooling. A significant contributi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f0ac6ccb2aa10383530f7b7cebbf5593
https://doi.org/10.1016/j.fusengdes.2015.01.034
https://doi.org/10.1016/j.fusengdes.2015.01.034
Autor:
V.R. Barabash, Igor Kedrov, Elena Privalova, A. Alekseev, J.-M. Martinez, Petr Savrukhin, C. Sborchia, Jan Umprecht, B. Giraud, Markus Prebeck, Thomas Schiller, Werner Koenig, Sergey Fabritsiev, Franz Ranzinger, James Davis, Evgeny Kuzmin, J. Guirao, B. Levesy, Samir Sfarni, Vincent Albin, Lubos Valenta, Chang Ho Choi, Y. Utin
Publikováno v:
Fusion Engineering and Design. :1643-1647
The ITER Vacuum Vessel (VV) features upper, equatorial and lower ports. The upper and regular equatorial ports are occupied by the port plugs. Although the port design has been overall completed in the past, the design of some remaining interfaces wa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a602fb8cb867e2dffb3e5ca857b6eb29
https://doi.org/10.1016/j.fusengdes.2015.06.025
https://doi.org/10.1016/j.fusengdes.2015.06.025
Publikováno v:
Fusion Engineering and Design. :2182-2186
The port plug test facility (PPTF) in the ITER hot cell building (HCB) will be used to test activated equatorial port plugs (EPP). The design of the PPTF and the HCB walls adjacent to the PPTF aims to have the docking room, which is next to the test
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f237bba2692884e80aa3fe79a4f542a2
https://doi.org/10.1016/j.fusengdes.2015.02.005
https://doi.org/10.1016/j.fusengdes.2015.02.005
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