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Results: 1-8 |
Results: 8
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
Model and mockup of demo ceramic breeding zone for testing in the IVV-2M reactor
Authors: Kapychev, V Gorokhov, V Davydov, D Demidov, V Kazennov, Y Tebus, V Frolov, V Shikov, A Shishkov, N Kovalenko, V Lopatkin, A Marachev, A Shishkin, V Strebkov, Y Men'kin, L Zyryanov, A
Citation: V. Kapychev et al., Model and mockup of demo ceramic breeding zone for testing in the IVV-2M reactor, FUSION TECH, 39(1), 2001, pp. 45-53
Development of ceramic breeding zone models and mock-up of a demo blanket for in-pile irradiation testing
Authors: Kapychev, V Davydov, D Demidov, V Kazennov, Y Tebus, V Frolov, V Shikov, A Shishkov, N Kovalenko, V Lopatkin, A Marachev, A Shishkin, V Strebkov, Y
Citation: V. Kapychev et al., Development of ceramic breeding zone models and mock-up of a demo blanket for in-pile irradiation testing, PLASMA D OP, 8(3), 2000, pp. 187-199
Russian DEMO-S reactor with continuous plasma burn
Authors: Shatalov, G Kirillov, I Sokolov, Y Strebkov, Y Vasiliev, N
Citation: G. Shatalov et al., Russian DEMO-S reactor with continuous plasma burn, FUSION ENG, 51-2, 2000, pp. 289-298
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
Materials and fabrication technology of modules intended for irradiation tests of blanket tritium-breeding zones in Russian fusion reactor projects
Authors: Kapychev, V Davydov, D Gorokhov, V Ioltukhovskiy, A Kazennov, Y Tebus, V Frolov, V Shikov, A Shishkov, N Kovalenko, V Shishkin, N Strebkov, Y
Citation: V. Kapychev et al., Materials and fabrication technology of modules intended for irradiation tests of blanket tritium-breeding zones in Russian fusion reactor projects, J NUCL MAT, 283, 2000, pp. 1429-1433
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
ITER reference breeding blanket design
Authors: Ferrari, M Bianchi, A Celentano, G Danner, W Enoeda, M Gerber, A Gohar, Y Gulden, W Ioki, K Kuroda, T Lopatkin, A Lucca, F Masson, X Mattas, R Mazzone, G Mustoe, J Parker, R Petrizzi, L Pizzuto, A Plenteda, R Poitevin, Y Raffray, R Roccella, M Roux, N Scaffidi-Argentina, F Simoneau, JP Strebkov, Y Zacchia, F
Citation: M. Ferrari et al., ITER reference breeding blanket design, FUSION ENG, 46(2-4), 1999, pp. 177-183
Risultati: 1-8 |