Zobrazeno 1 - 10
of 55
pro vyhledávání: '"X. Raepsaet"'
Autor:
A. Negrini, H.J Brockmann, Jan Leen Kloosterman, F. Dolci, Nicola Cerullo, J. Magill, U. Ohlig, H.J. Ruetten, R. Seiler, F. Damian, W. von Lensa, J. C. Kuijper, Guglielmo Lomonaco, W. Bernnat, X. Raepsaet, J. B. M. De Haas, J. Oppe
Publikováno v:
Nuclear Engineering and Design. 236:615-634
The high-temperature gas-cooled reactor (HTGR) appears as a good candidate for the next generation of nuclear power plants. In the “HTR-N” project of the European Union Fifth Framework Program, analyses have been performed on a number of conceptu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7947bc251ad58d4371a87488f253c3da
https://doi.org/10.1016/j.nucengdes.2005.10.021
https://doi.org/10.1016/j.nucengdes.2005.10.021
Publikováno v:
Progress in Nuclear Energy. 38:415-418
In the framework of a large Research and Development programme devoted to High Temperature Reactors (HTR) and set up in the CEA from 2000 on, we will address ourselves to the issue of coated fuel performance and design. Although HTR fuel main feature
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::05f0c584cee6112c9b3f0d67d7d9da67
https://doi.org/10.1016/s0149-1970(00)00148-7
https://doi.org/10.1016/s0149-1970(00)00148-7
Publikováno v:
Fusion Engineering and Design. :921-926
The Helium Cooled Pebble Bed (HCPB) blanket is one of the two concepts to be further developed for a European DEMO power reactor. Tritium leakage due to the permeation through the main structural materials constitutes one of the main problems of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::212b00e59e04e897ea3b67cdce11faf7
https://doi.org/10.1016/s0920-3796(00)00339-2
https://doi.org/10.1016/s0920-3796(00)00339-2
Publikováno v:
Fusion Engineering and Design. 29:225-232
The potential sources of tritium contamination of the helium coolant of ceramic breeder blankets have previously been evaluated for the specific case of the European BIT DEMO blanket. This confirmed that the control of tritium losses to the steam cir
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::07ae88a92c04a2d91d76e25074f6f2a5
https://doi.org/10.1016/0920-3796(95)80028-v
https://doi.org/10.1016/0920-3796(95)80028-v
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 Engineering and Design. 17:367-372
One of the objectives assigned to a DEMO blanket will be to limit tritium leakage to the steam circuit by permeation through the steam generator tubing of the tritium unavoidably present in the coolant. The control of these losses will require, on on
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2a5762ac0e724efc9c764e34cf0c6553
https://doi.org/10.1016/0920-3796(91)90082-2
https://doi.org/10.1016/0920-3796(91)90082-2
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::de66fcf9e8d44498e6001542f91ec06c
https://doi.org/10.1016/0920-3796(91)90045-r
https://doi.org/10.1016/0920-3796(91)90045-r
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...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c3ea3b5d316f4279b2668cbd2a501ee1
https://doi.org/10.13182/fst91-a29465
https://doi.org/10.13182/fst91-a29465
Publikováno v:
Nuclear Engineering and Design, 222
In the frame of the European contract HTR-N, a work package is devoted to the code validation and method improvements as far as the high temperature gas-cooled reactor (HTGR) core modelling is concerned. Institutions from three countries are involved
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::17b3a956dd543d3dd859676f70cd0d29
https://doi.org/10.1016/s0029-5493(03)00026-8
https://doi.org/10.1016/s0029-5493(03)00026-8
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