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Results: 1-15 |
Results: 15
ITER R&D: Vacuum vessel and in-vessel components: Shield blanket module
Authors: Danner, W Cardella, A Ioki, K Mattas, R Ohara, Y Strebkov, Y
Citation: W. Danner et al., ITER R&D: Vacuum vessel and in-vessel components: Shield blanket module, FUSION ENG, 55(2-3), 2001, pp. 205-217
ITER-FEAT vacuum vessel and blanket design features and implications for the R&D programme
Authors: Ioki, K Danner, W Koizumi, K Krylov, VA Cardella, A Elio, F Onozuka, M
Citation: K. Ioki et al., ITER-FEAT vacuum vessel and blanket design features and implications for the R&D programme, NUCL FUSION, 41(3), 2001, pp. 265-275
Main achievements of the EU HT test programme of ITER primary wall small scale mock ups
Authors: Lorenzetto, P Cardella, A Chappuis, P Daenner, W Erskine, A Febvre, M Hofmann, G Le Gallo, P Stamm, H Tahtinen, S
Citation: P. Lorenzetto et al., Main achievements of the EU HT test programme of ITER primary wall small scale mock ups, FUSION ENG, 49, 2000, pp. 263-268
Manufacturing of a full scale baffle prototype for ITER with a CFC and W plasma spray armour
Authors: Merola, M Bobin-Vastra, I Cardella, A Febvre, M Giancarli, L Plochl, L Salavy, JF Salito, A Schedler, B Vieider, G
Citation: M. Merola et al., Manufacturing of a full scale baffle prototype for ITER with a CFC and W plasma spray armour, FUSION ENG, 49, 2000, pp. 289-294
Major achievements of the European shield blanket R&D during the ITER EDA,and their relevance for future next step machines
Authors: Danner, W Cardella, A Jones, L Lorenzetto, P Maisonnier, D Malavasi, G Peacock, A Rodgers, E Tavassoli, F
Citation: W. Danner et al., Major achievements of the European shield blanket R&D during the ITER EDA,and their relevance for future next step machines, FUSION ENG, 49, 2000, pp. 425-433
FW/Blanket and vacuum vessel for RTO/RC ITER
Authors: Ioki, K Barabash, V Cardella, A Elio, F Iida, H Johnson, G Kalinin, G Miki, N Onozuka, M Sannazzaro, G Utin, Y Yamada, M
Citation: K. Ioki et al., FW/Blanket and vacuum vessel for RTO/RC ITER, FUSION ENG, 49, 2000, pp. 467-475
Improved modules for the blanket of RTO/RC ITER
Authors: Elio, F Ioki, K Cardella, A
Citation: F. Elio et al., Improved modules for the blanket of RTO/RC ITER, FUSION ENG, 49, 2000, pp. 535-541
Application of beryllium as first wall armour for ITER primary, baffle andlimiter modules
Authors: Cardella, A Barabash, V Ioki, K Yamada, M Hatano, T Ohara, Y Lorenzetto, P Merola, M Mazul, I Strebkov, Y
Citation: A. Cardella et al., Application of beryllium as first wall armour for ITER primary, baffle andlimiter modules, FUSION TECH, 38(3), 2000, pp. 326-333
Design and fabrication methods of FW/blanket, divertor and vacuum vessel for ITER
Authors: Ioki, K Barabash, V Cardella, A Elilo, F Ibbott, C Janeschitz, J Johnson, G Kalinin, G Miki, N Onozuka, M Sannazzaro, G Tivey, R Utin, Y Yamada, M
Citation: K. Ioki et al., Design and fabrication methods of FW/blanket, divertor and vacuum vessel for ITER, J NUCL MAT, 283, 2000, pp. 957-961
Effects of plasma disruption events on ITER first wall materials
Authors: Cardella, A Gorenflo, H Lodato, A Ioki, K Raffray, R
Citation: A. Cardella et al., Effects of plasma disruption events on ITER first wall materials, J NUCL MAT, 283, 2000, pp. 1105-1110
Armor and heat sink materials joining technologies development for ITER plasma facing components
Authors: Barabash, V Akiba, M Cardella, A Mazul, I Odegard, BC Plochl, L Tivey, R Vieider, G
Citation: V. Barabash et al., Armor and heat sink materials joining technologies development for ITER plasma facing components, J NUCL MAT, 283, 2000, pp. 1248-1252
Assessment and selection of materials for ITER in-vessel components
Authors: Kalinin, G Barabash, V Cardella, A Dietz, J Ioki, K Matera, R Santoro, RT Tivey, R
Citation: G. Kalinin et al., Assessment and selection of materials for ITER in-vessel components, J NUCL MAT, 283, 2000, pp. 10-19
Engineering design of the ITER blanket and relevant research and development results
Authors: Elio, F Ioki, K Barabaschi, P Bruno, L Cardella, A Hechler, M Kodama, T Lodato, A Loesser, D Lousteau, D Miki, N Mohri, K Parker, R Raffray, R Williamson, D Yamada, M Daenner, W Mattas, R Strebkov, Y Takatsu, H
Citation: F. Elio et al., Engineering design of the ITER blanket and relevant research and development results, FUSION ENG, 46(2-4), 1999, pp. 159-175
Design of the ITER shielding blanket
Authors: Lousteau, D Ioki, K Bruno, L Cardella, A Elio, F Hechler, M Kodama, T Lodato, A Loesser, D Miki, N Mohri, K Raffray, R Yamada, M
Citation: D. Lousteau et al., Design of the ITER shielding blanket, FUSION TECH, 34(3), 1998, pp. 384-389
Design and material selection for ITER first wall/blanket, divertor and vacuum vessel
Authors: Ioki, K Barabash, V Cardella, A Elio, F Gobar, Y Janeschitz, G Johnson, G Kalinin, G Lousteau, D Onozuka, M Parker, R Sannazzaro, G Tivey, R
Citation: K. Ioki et al., Design and material selection for ITER first wall/blanket, divertor and vacuum vessel, J NUCL MAT, 263, 1998, pp. 74-84
Risultati: 1-15 |