Zobrazeno 1 - 10
of 17
pro vyhledávání: '"J. Quintric-Bossy"'
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...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2590f077098520b737447abeda4f7108
https://doi.org/10.13182/fst94-a40297
https://doi.org/10.13182/fst94-a40297
Publikováno v:
Fusion Technology. 21:2081-2088
Within the framework of the European DEMO blanket study programme, this paper describes the design work performed on the “box-shaped” concept for water-cooled Pb-17Li blankets in the past two years. The first part of the paper describes the gener
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c3ffceb1a3e5430cece7f8092d1556ab
https://doi.org/10.13182/fst92-a30028
https://doi.org/10.13182/fst92-a30028
Publikováno v:
Fusion Engineering and Design. 17:249-255
Within the framework of the European DEMO blanket study programme, CEA and the JRC of Ispra are jointly developing a water-cooled lithium-lead blanket concept. The new DEMONET reactor configuration released in Spring 1990 and currently specified in t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ba815e912ea26c69be832b237a974b3a
https://doi.org/10.1016/0920-3796(91)90066-y
https://doi.org/10.1016/0920-3796(91)90066-y
Publikováno v:
Fusion Technology. 19:1006-1011
Within the framework of the European DEMO blanket study programme, CEA and the JRC of ISPRA develop a water cooled lithium-lead blanket concept. Considering the low breeding coverage ratio of the D...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d37ddfea83c4295340fb248d2bd751dc
https://doi.org/10.13182/fst91-a29474
https://doi.org/10.13182/fst91-a29474
Autor:
L. Baraer, G. Casini, F. Farfaletti-Casali, J. Wu, Y. Severi, M. Rieger, M. Biggio, Massimo Zucchetti, M. Roze, G. Gervaise, S. Tominetti, J. Quintric-Bossy, Ph. Labbe, L. Giancarli
Publikováno v:
Fusion Engineering and Design. 14:353-372
The main features of a tritium breeding blanket for a Demonstration Power Reactor involving the eutectic Pb-17Li as liquid breeder and water as coolant are presented. The configuration of the blanket segments and breeder modules as well as their arra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::98dec5bf69210d43e0d077e2e2a68178
https://doi.org/10.1016/0920-3796(91)90019-m
https://doi.org/10.1016/0920-3796(91)90019-m
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1fd0bf3745732dea5bc7dd28f8029acc
https://doi.org/10.1109/fusion.1993.518272
https://doi.org/10.1109/fusion.1993.518272
Autor:
L. Giancarli, B. Bielak, P. Chappuis, C. Cheron, G. Le Marois, Y. Poitevin, J. Quintric-Bossy, J.-F. Salavy, Y. Severi, J. Szczepanski
The present paper describes the ITER outboard baffle design including the choice of armor and heat sink first wall materials. Two versions of first wall attachment are presented which differ from the applied fabrication techniques. The choice of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0c7fbadd4401c164d7d552fe0e5f7000
https://doi.org/10.1016/b978-0-444-82762-3.50035-5
https://doi.org/10.1016/b978-0-444-82762-3.50035-5
The development of the water-cooled lithium-lead box-shaped blanket concept for DEMO has now reached the stage of thermo-mechanical optimization. In the previous design phases the preliminary dimensioning of the cooling circuit has permitted to defin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2bcab091764256f90c2fd6abe1596733
https://doi.org/10.1016/b978-0-444-89995-8.50291-5
https://doi.org/10.1016/b978-0-444-89995-8.50291-5
Publisher Summary This chapter discusses the investigation of water cooled lithium–lead blankets jointly performed by CEA and the JRC of ISPRA in the framework of the European DEMO blanket study program. The reactor characteristics considered in th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f4a3cea230767d9d9ba0fe44b5c77cca
https://doi.org/10.1016/b978-0-444-88508-1.50182-1
https://doi.org/10.1016/b978-0-444-88508-1.50182-1
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