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Publikováno v:
Fusion Science and Technology. 61:321-331
There is a strong indication that the dual-cooled LiPb blanket is the preferred concept for many fusion power plants being designed around the world. The ability of the blanket to provide tritium s...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::82d2e20fb2351e4ec81404f03c44a805
https://doi.org/10.13182/fst11-451
https://doi.org/10.13182/fst11-451
Autor:
David A. Petti, Mark S. Tillack, Farrokh Najmabadi, S. Malang, P. West, Brad J. Merrill, A. Abdou, V.C. Chan, Ronald L. Miller, T. K. Mau, Paul P. H. Wilson, G.M. Syaebler, A.R. Raffray, Thomas Brown, M.C. Chu, Don Steiner, E. A. Mogahed, L. L. Lao, F. Dahlgren, X. R. Wang, I.N. Sviatoslavsky, Douglass L. Henderson, C.E. Kessel, Leslie Bromberg, P. A. Politzer, T.W. Petrie, Laila El-Guebaly, G. R. Longhurst, H.E. St. John, P.J. Heitzenroeder, Lester M. Waganer, P. Synder, A. D. Turnbull, R. L. Moore
Publikováno v:
Fusion Engineering and Design. 80:3-23
The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant and to identifying physics and technology areas with the highest leverage for achieving attractive
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3cb69dcd21575f83b39413c4cce24941
https://doi.org/10.1016/j.fusengdes.2005.11.003
https://doi.org/10.1016/j.fusengdes.2005.11.003
Publikováno v:
Fusion Science and Technology. 47:1074-1078
The key issues associated with the three maintenance approaches envisaged for the Compact Stellarator (CS) power core have been identified and addressed, and the layout of coil system, coil supporting structure, cryostats, vacuum vessel and maintenan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6578011f74186ce00c8a210266cd46cc
https://doi.org/10.13182/fst05-a829
https://doi.org/10.13182/fst05-a829
Publikováno v:
Fusion Engineering and Design. 69:227-231
Beryllium in form of pebbles with diameter of about 1 mm is foreseen as neutron multiplier in the European helium cooled pebble bed (HCPB) blanket for fusion power plants. The pebbles are arranged in beds between flat cooling plates. During operation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eeaba4e71431fe40a76fd2b7225caa8d
https://doi.org/10.1016/s0920-3796(03)00344-2
https://doi.org/10.1016/s0920-3796(03)00344-2
Autor:
S Malang, S Hermsmeyer
Publikováno v:
Fusion Engineering and Design. :197-202
Designing divertor target plates for a fusion power plant is a challenging task because they have to allow exceptionally high heat fluxes, deliver heat to the power conversion system at a temperature suitable for high efficiency, and use a coolant co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c4200e44e2a35158119da64b68b4d526
https://doi.org/10.1016/s0920-3796(02)00174-6
https://doi.org/10.1016/s0920-3796(02)00174-6
Publikováno v:
Fusion Engineering and Design. :283-293
First wall and blanket (FW/blanket) design is a crucial element in the performance and acceptance of a fusion power plant. High temperature structural and breeding materials are needed for high thermal performance. A suitable combination of structura
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4359eec6da978d5a9bd288dbb28498af
https://doi.org/10.1016/s0920-3796(02)00295-8
https://doi.org/10.1016/s0920-3796(02)00295-8
Autor:
R. Conrad, J.G. van der Laan, B.J Pijlgroms, J. Reimann, M. Jong, S. Malang, L.V. Boccaccini, A.J. Magielsen, M.P Stijkel, J.H Fokkens
Publikováno v:
Fusion Engineering and Design. :383-390
In the framework of developing the helium cooled pebble-bed (HCPB) blanket an irradiation test of pebble-bed assemblies is prepared at the HFR Petten. The test objective is to concentrate on the effect of neutron irradiation on the thermal-mechanical
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d1236ba19ff5e650bc4857f3a865e367
https://doi.org/10.1016/s0920-3796(02)00294-6
https://doi.org/10.1016/s0920-3796(02)00294-6
Autor:
C. E. Kessel, F. M. Poli, K. Ghantous, N. Gorelenkov, M. S. Tillack, F. Najmabadi, X. R. Wang, D. Navaei, H. H. Toudeshki, C. Koehly, L. El-Guebaly, J. P. Blanchard, C. J. Martin, L. Mynsburge, P. Humrickhouse, M. E. Rensink, T. D. Rognlien, M. Yoda, S. I. Abdel-Khalik, M. D. Hageman, B. H. Mills, J. D. Radar, D. L. Sadowski, P. B. Snyder, H. John, A. D. Turnbull, L. M. Waganer, S. Malang, A. F. Rowcliffe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::74c9e75af751036110dd2efd22e5318b
https://doi.org/10.2172/1127358
https://doi.org/10.2172/1127358
Publikováno v:
Fusion Engineering and Design. :369-373
In fusion power plant divertors a significant portion of the total fusion power is absorbed. In order to achieve a high thermal plant efficiency this power has to be removed at high temperature levels. This calls for innovative designs which differ f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2b107a3b43e5fd2f0c9589401eb54c3e
https://doi.org/10.1016/s0920-3796(01)00326-x
https://doi.org/10.1016/s0920-3796(01)00326-x