Consistent integration in preparing the helium cooled lithium lead DEMO-2007 reactor
作者： A. Li-Puma , J. Bonnemason , L. Cachon , J.L. Duchateau , F. Gabriel
DOI: 10.1016/J.FUSENGDES.2009.01.097
关键词:
摘要: Abstract Within the European fusion programme, helium cooled lithium lead (HCLL) breeding blanket is one of concepts to be pursued as possible candidates for DEMO reactor. A HCLL-DEMO reactor has been assessed in 2007, a near term power plant based on limited technologies and plasma extrapolation from ITER. In this frame, paper presents results activities carried out by CEA teams, including both vessel ex components. The high interdependency between several technological components highlighted. careful integrated assessment further account integration all machine towards final robust consistent version also recommended future activity.
elsevier.com
sci-hub.se 参考文章(38)
J L Duchateau, P Hertout, Which superconducting material for the toroidal field system of the fusion DEMO reactor Journal of Physics: Conference Series. ,vol. 97, pp. 012038- ,(2008) , 10.1088/1742-6596/97/1/012038
Y. Poitevin, L.V. Boccaccini, A. Cardella, L. Giancarli, R. Meyder, E. Diegele, R. Laesser, G. Benamati, The European breeding blankets development and the test strategy in ITER symposium on fusion technology. ,vol. 75, pp. 741- 749 ,(2005) , 10.1016/J.FUSENGDES.2005.06.296
G. Aiello, F. Gabriel, L. Giancarli, G. Rampal, J.-F. Salavy, Thermal–hydraulic analysis of the HCLL DEMO blanket symposium on fusion technology. ,vol. 82, pp. 2189- 2194 ,(2007) , 10.1016/J.FUSENGDES.2007.08.003
C Gormezano, A.C.C Sips, T.C Luce, S Ide, A Becoulet, X Litaudon, A Isayama, J Hobirk, M.R Wade, T Oikawa, R Prater, A Zvonkov, B Lloyd, T Suzuki, E Barbato, P Bonoli, C.K Phillips, V Vdovin, E Joffrin, T Casper, J Ferron, D Mazon, D Moreau, R Bundy, C Kessel, A Fukuyama, N Hayashi, F Imbeaux, M Murakami, A.R Polevoi, H.E. St John, Chapter 6: Steady state operation Nuclear Fusion. ,vol. 47, ,(2007) , 10.1088/0029-5515/47/6/S06
J.L Duchateau, J.Y Journeaux, F Millet, Estimation of the recycled power associated with the cryogenic refrigeration power of a fusion reactor based on TORE SUPRA experiment and ITER design Nuclear Fusion. ,vol. 46, ,(2006) , 10.1088/0029-5515/46/3/S13
K. Tobita, S. Nishio, M. Enoeda, M. Sato, T. Isono, S. Sakurai, H. Nakamura, S. Sato, S. Suzuki, M. Ando, K. Ezato, T. Hayashi, T. Hayashi, T. Hirose, T. Inoue, Y. Kawamura, N. Koizumi, Y. Kudo, R. Kurihara, T. Kuroda, M. Matsukawa, K. Mouri, Y. Nakamura, M. Nishi, Y. Nomoto, J. Ohmori, N. Oyama, K. Sakamoto, T. Suzuki, M. Takechi, H. Tanigawa, K. Tsuchiya, D. Tsuru, Design study of fusion DEMO plant at JAERI Fusion Engineering and Design. ,vol. 81, pp. 1151- 1158 ,(2006) , 10.1016/J.FUSENGDES.2005.08.058
Ulrich Fischer, Impact of ports on the breeding performance of liquid metal and solid breeder blankets in the DEMONET configuration Fusion Engineering and Design. ,vol. 18, pp. 323- 329 ,(1991) , 10.1016/0920-3796(91)90146-H
D. Ward, P. Sardain, D. Maisonnier, L. Di Pace, L. Giancarli, A. Li Puma, P. Norajitra, A. Orden, E. Arenaza, The European power plant conceptual study: Helium-cooled lithium–lead reactor concept Fusion Engineering and Design. ,vol. 81, pp. 2673- 2678 ,(2006) , 10.1016/J.FUSENGDES.2006.07.056
Michael A Fütterer, Helmut Albrecht, Pierre Giroux, Manfred Glugla, Hiroshi Kawamura, Otto K Kveton, David K Murdoch, Dai-Kai Sze, Tritium technology for blankets of fusion power plants Fusion Engineering and Design. ,vol. 49, pp. 735- 743 ,(2000) , 10.1016/S0920-3796(00)00204-0
Edgar Bogusch, Mihaela Ionescu-Bujor, Alain Chevalier, Bogdan Bielak, Synergies between FNT developments and advanced nuclear fission technologies Fusion Engineering and Design. ,vol. 81, pp. 1667- 1674 ,(2006) , 10.1016/J.FUSENGDES.2005.08.029