Zobrazeno 1 - 10
of 78
pro vyhledávání: '"J.P. Friconneau"'
Publikováno v:
Fusion Engineering and Design. 136:1342-1347
Since the ITER Casks will be not shielded, human access will be forbidden in trajectory zones and, in the event of failure of Cask and Plug Remote Handling System (CPRHS) functions, rescue operations will have to be remotely conducted. As potential f
Autor:
David Hamilton, M. Saito, Philip Bates, M. Van Uffelen, D. Locke, C. Van Hille, Emilio Ruiz, J.P. Friconneau, Y. Noguchi, Chang-Hwan Choi, S. Murakami, Carlo Damiani, Roger Reichle, S. Bernal, L. Mont, Nobukazu Takeda, M. Lewczanin, S. Balagué, J. Sanchez Cuevas, Gregory Dubus, Salvador Esque, J.P. Martin, R. Shuff, T. Maruyama, Adrian Puiu, Carmen González, N. Van De Ven, J. Cornellá, B. Perrier, T. Ilkei, C. Annino, J. Palmer
Publikováno v:
Fusion Engineering and Design. 136:1117-1124
For a first-of-a-kind nuclear fusion reactor like ITER, remote maintainability of neutron-activated and contaminated components is one of the key aspects of plant design and operations, hence a fundamental ingredient of its success, as well as of the
Autor:
Stephane Gazzotti, F. Ferlay, K. Huc, P. Viudes, L. Meunier, J-P Martins, J.P. Friconneau, B. Peluso, A. Derkazarian
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, Elsevier, 2021, 172, pp.112780. ⟨10.1016/j.fusengdes.2021.112780⟩
Fusion Engineering and Design, 2021, 172, pp.112780. ⟨10.1016/j.fusengdes.2021.112780⟩
Fusion Engineering and Design, Elsevier, 2021, 172, pp.112780. ⟨10.1016/j.fusengdes.2021.112780⟩
Fusion Engineering and Design, 2021, 172, pp.112780. ⟨10.1016/j.fusengdes.2021.112780⟩
International audience; As augmented and virtual reality technology is revolutionising the way products are designed and tested, many companies are expanding the range of use cases across their organisations. After 10 years using Virtual Reality (VR)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::891a4f726e95dcbf011e560f09710b07
https://hal.archives-ouvertes.fr/hal-03285691
https://hal.archives-ouvertes.fr/hal-03285691
Publikováno v:
Fusion Engineering and Design. 124:673-676
ITER is a large scale fusion device designed to study the high temperature fusion reaction between tritium and deuterium. The success of a tokamak-type fusion reactor will depend to a great extent on developing reliable and safe methods of carrying o
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
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, Elsevier, 2018, 132, pp.90-98. ⟨10.1016/j.fusengdes.2018.04.027⟩
Fusion Engineering and Design, 2018, 132, pp.90-98. ⟨10.1016/j.fusengdes.2018.04.027⟩
Fusion Engineering and Design, Elsevier, 2018, 132, pp.90-98. ⟨10.1016/j.fusengdes.2018.04.027⟩
Fusion Engineering and Design, 2018, 132, pp.90-98. ⟨10.1016/j.fusengdes.2018.04.027⟩
International audience; The Remote Handling tasks scheduled during the ITER maintenance shutdown require transportation of in-vessel components and remote-handling tools from the Vacuum Vessel (VV) ports to the Hot Cell Building (HCB). These componen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e79ee8aa4fc859d13efab59270bfbb52
https://hal-cea.archives-ouvertes.fr/cea-02428761/file/1-s2.0-S0920379618303156-main.pdf
https://hal-cea.archives-ouvertes.fr/cea-02428761/file/1-s2.0-S0920379618303156-main.pdf
Autor:
A. Dammann, V. Beaudoin, C. Dremel, J.P. Friconneau, L. Antola, D. Evrard, A. Lemée, B. Levesy, C.S. Pitcher
Publikováno v:
Fusion Engineering and Design. :1457-1460
Internal components of the ITER Tokamak are replaced and transferred to the Hot Cell by remote handling equipment. These components include port plugs, cryopumps, divertor cassettes, blanket modules, etc. They are brought to the refurbishment area of
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:
D. Locke, K. Olajos, Salvador Esque, C. Annino, C. Van Hille, R. Shuff, Adrian Puiu, J.P. Friconneau, T. Di Mascio, L. Mont, Roberto Ranz, S. Balagué, M. Lewczanin, Chang-Hwan Choi, Philip Bates, J. Palmer, F. Ceccanti, M. Van Uffelen, C. Gonzalez, Carlo Damiani, David Hamilton, Gregory Dubus, A. Tesini
Publikováno v:
Fusion Engineering and Design. 89:2251-2256
For a first-of-a-kind nuclear fusion reactor like ITER, remote maintainability of neutron-activated components is one of the key aspects of plant design and operations, and a fundamental ingredient for the demonstration of long-term viability of fusi
Autor:
J.P. Friconneau, Pierre Cortes, A. Siarras, Krishan Kumar Gotewal, J.-C. Nevière, M. Iseli, B. Levesy, J.P. Martins, A. Tesini, Laurent Patisson, Mario Merola, Byoung-Yoon Kim, R. Pascal, L. Giancarli
Publikováno v:
Fusion Engineering and Design. 88:2417-2421
Each Test Blanket System in ITER is formed by an in-vessel component, the Test Blanket Module, and several associated ancillary systems (coolant and Tritium systems, instrumentation and control systems). The paper describes the overall replacement/ma