Zobrazeno 1 - 10
of 31
pro vyhledávání: '"B. Bielak"'
Autor:
J.-F. Salavy, B. Bielak, J Reimann, O.V Ogorodnikova, Y. Severi, Yves Poitevin, M.A Fütterer, J. Szczepanski, G. Marbach, Gianluca Benamati, L. Giancarli, C. Nardi
Publikováno v:
Fusion Engineering and Design. 46:185-192
This paper presents a short description of the latest design version of the water-cooled Pb–17Li test-blanket module system and the proposal for the test program to be performed during the ITER Basic Performance Phase. The present R&D program fores
Autor:
C. Nardi, K Schleisiek, A. Li Puma, J.-F. Salavy, B. Bielak, L. Giancarli, C Dellis, J.P Deffain, M.A Fütterer, J. Szczepanski
Publikováno v:
Fusion Engineering and Design. :851-858
In 1996, the European Community started the development of a water-cooled Pb-17Li blanket test module for ITER. First tests are currently scheduled to start with the beginning of the Basic Performance Phase prior to d–t operation. The test module i
Autor:
L.A. Sedano, L. Baraer, J. Quintric-Bossy, Y. Severi, M.A Fütterer, M. Eid, X. Raepsaet, C. Nardi, B. Bielak, E. Proust, L. Giancarli, L. Petrizzi, J.-F. Salavy
Publikováno v:
Fusion Technology. 26:1079-1085
The water-cooled Pb-17Li blankets represent one of the blanket lines selected within the European Union for DEMO-relevant design and R&D activities. This paper gives a presentation of the reference...
Publikováno v:
Fusion Technology. 21:2152-2158
This paper presents the recent development studies on the adaptation of the European Ceramic BIT Blanket to updated DEMO specifications. The adaptation work is in progress, since 1990, when a detai...
Autor:
B. Gouton, F. Carre, J. Szczpaksi, W. Daenner, P. Lorenzetto, P. Hubert, D. Besson, J. Mercier, L. Giancarli, F. Gervaise, G. Stalport, P. Thomas, B. Bielak, G. Mignot
Publikováno v:
Fusion Engineering and Design. 17:287-291
After a brief summary of the work performed within the frame of the NET Shielding Blanket segment predesign and manufacturing feasibility study, which first phase has been recently completed, this paper gives the outlines of a first development phase
Autor:
J. Mercier, M. Gallina, L. Baraer, L. Giancarli, S. Cevolani, V. Zampaglione, B. Bielak, J. Szczepanski, F. Vallette, V. Rado, V. Violante, E. Proust, V. Vettraino, P. Cecchi, L. Anzidei, Luigino Petrizzi, C. Talarico, X. Raepsaet
Publikováno v:
Fusion Engineering and Design. 17:117-122
The DEMO specifications defined so as to ensure the consistency of the various blanket conceptual design studies performed within the framework of the European Test Blanket Program me have been recently updated. A very first attempt has been made to
Autor:
M. Gouton, G. Vieider, P. Thomas, W. Daenner, P. Hubert, D. Besson, F. Carre, B. Bielak, F. Mercier, G. Stalport
Publikováno v:
Fusion Technology. 19:1051-1056
This paper summarizes the main conclusions of a study contracted by the NET Team to the CEA, with Framatome as subcontractor, to perform predesign and feasibility studies of the NET shielding blank...
Autor:
B. Bielak, J. Szczepanski, V. Violante, S. Cevolani, J. Mercier, P. Cecchi, L. Anzidei, L. Giancarli, V. Rado, Luigino Petrizzi, V. Zampaglione, V. Vettraino, F. Gervaise, F. Vallette, X. Raepsaet, M. Gallina, E. Proust, L. Baraer
Publikováno v:
Fusion Technology. 19:944-950
A blanket option featured by helium cooling and lithiated ceramics inside tubes is under development at CEA/ENEA within the framework of the European Test Blanket Program. A first conceptual design...
Autor:
Gianfranco Caruso, O. Asuar Alonso, A. Naviglio, Nelson Martins, J. R. Humphries, S. Nisan, G Mini, L. Volpi, B. Bielak
This paper summarises our recent investigations undertaken as part of the EURODESAL project on nuclear desalination, currently being carried out by a consortium of four European, and one Canadian, industrials and two leading EU R&D organisations. Maj
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::77b61be61f6fa8623c1cf346dd599a24
http://hdl.handle.net/11573/381118
http://hdl.handle.net/11573/381118
Autor:
L. Baraer, E. Proust, J. Quintric-Bossy, X. Raepsaet, L. Giancarli, L.A. Sedano, J. Szczepanski, Y. Severi, J.-F. Salavy, B. Bielak
Publikováno v:
15th IEEE/NPSS Symposium. Fusion Engineering.
For several years the EC laboratories have developed breeding blankets for DEMO. From this experience, it has been derived a proposal of tritium breeding blanket for the Extended Performance Phase (EPP) of ITER. The general basic ideas are the follow