-
1
-
-
0036864282
-
Advanced high performance solid wall blanket concepts
-
Wong C.P.C., Malang S., Nishio S., Raffray R., and Sagara A. Advanced high performance solid wall blanket concepts. Fusion Eng. Des. 61-62 (November) (2002) 283-293
-
(2002)
Fusion Eng. Des.
, vol.61-62 November
, pp. 283-293
-
-
Wong, C.P.C.1
Malang, S.2
Nishio, S.3
Raffray, R.4
Sagara, A.5
-
2
-
-
34948857964
-
Recent progress in DEMO fusion core engineering: improved segmentation, maintenance and blanket concepts
-
Ihli T., Boccaccini L.V., Janeschitz G., Koehly C., Maisonnier D., Nagy D., Polixa C., Rey J., and Sardain P. Recent progress in DEMO fusion core engineering: improved segmentation, maintenance and blanket concepts. Fusion Eng. Des. 82 15-24 (2007) 2705-2712
-
(2007)
Fusion Eng. Des.
, vol.82
, Issue.15-24
, pp. 2705-2712
-
-
Ihli, T.1
Boccaccini, L.V.2
Janeschitz, G.3
Koehly, C.4
Maisonnier, D.5
Nagy, D.6
Polixa, C.7
Rey, J.8
Sardain, P.9
-
3
-
-
57049156144
-
High availability remote maintenance approach for the European DEMO breeder blanket options
-
Chengdu, China
-
Ihli T., Nagy D., Koehly C., and Rey J. High availability remote maintenance approach for the European DEMO breeder blanket options. Poceedings of the IAEA Technical Meeting. Chengdu, China (October 16-21, 2006)
-
(2006)
Poceedings of the IAEA Technical Meeting
-
-
Ihli, T.1
Nagy, D.2
Koehly, C.3
Rey, J.4
-
4
-
-
4243628887
-
Advanced helium cooled pebble bed blanket with SiCf/SiC as structural material
-
Boccaccini L.V., Fischer U., Gordeev S., and Malang S. Advanced helium cooled pebble bed blanket with SiCf/SiC as structural material. Fusion Eng. Des. 49-50 (November 2000) 491-497
-
(2000)
Fusion Eng. Des.
, vol.49-50
, pp. 491-497
-
-
Boccaccini, L.V.1
Fischer, U.2
Gordeev, S.3
Malang, S.4
-
5
-
-
57049143821
-
Prototype fusion reactor based on SiC/SiC composite material focusing on easy maintenance
-
Culham
-
Nishio S. Prototype fusion reactor based on SiC/SiC composite material focusing on easy maintenance. Proceedings of the IAEA-TCM on Fusion Power Plant Design. Culham (March 24-27, 1998)
-
(1998)
Proceedings of the IAEA-TCM on Fusion Power Plant Design
-
-
Nishio, S.1
-
6
-
-
57049183178
-
Status of EC solid breeder-blanket designs and R&D for DEMO fusion reactors, Fusion Engineering and Design, Volume 27
-
Dalle Donne M., Anzidei L., Kwast H., Moons F., and Proust E. Status of EC solid breeder-blanket designs and R&D for DEMO fusion reactors, Fusion Engineering and Design, Volume 27. Proceedings of the Third International Symposium on Fusion Nuclear Technology (March 1, 1995) 319-336
-
(1995)
Proceedings of the Third International Symposium on Fusion Nuclear Technology
, pp. 319-336
-
-
Dalle Donne, M.1
Anzidei, L.2
Kwast, H.3
Moons, F.4
Proust, E.5
-
7
-
-
27844479100
-
The European breeding blankets development and the test strategy in ITER, Fusion Engineering and Design, vol. 75-79
-
Poitevin Y., Boccaccini L.V., Cardella A., Giancarli L., Meyder R., Diegele E., Laesser R., and Benamati G. The European breeding blankets development and the test strategy in ITER, Fusion Engineering and Design, vol. 75-79. Proceedings of the 23rd Symposium of Fusion Technology-SOFT 23 (November 2005) 741-749
-
(2005)
Proceedings of the 23rd Symposium of Fusion Technology-SOFT 23
, pp. 741-749
-
-
Poitevin, Y.1
Boccaccini, L.V.2
Cardella, A.3
Giancarli, L.4
Meyder, R.5
Diegele, E.6
Laesser, R.7
Benamati, G.8
-
8
-
-
0007659248
-
Dual-coolant liquid metal breeder blanket
-
Malang S., Bojarski E., Bfihler L., Deckers H., Fischer U., Norajitra P., and Reiser H. Dual-coolant liquid metal breeder blanket. Fusion Technology 1992: Proceedings of the 17th SOFT (1992) 1424-1428
-
(1992)
Fusion Technology 1992: Proceedings of the 17th SOFT
, pp. 1424-1428
-
-
Malang, S.1
Bojarski, E.2
Bfihler, L.3
Deckers, H.4
Fischer, U.5
Norajitra, P.6
Reiser, H.7
-
10
-
-
0037323310
-
Fusion power core engineering for the ARIES-ST power plant
-
Tillack M.S., Wang X.R., Pulsifer J., Malang S., Sze D.K., Billone M., et al. Fusion power core engineering for the ARIES-ST power plant. Fusion Eng. Des. 65 2 (Feb 2003) 215-261
-
(2003)
Fusion Eng. Des.
, vol.65
, Issue.2
, pp. 215-261
-
-
Tillack, M.S.1
Wang, X.R.2
Pulsifer, J.3
Malang, S.4
Sze, D.K.5
Billone, M.6
-
11
-
-
57049131658
-
-
P. Norajitra, L. Bühler, A. Buenaventura, E. Diegele, U. Fischer, S. Gordeev, et al., Conceptual design of the dual-coolant blanket within the framework of the EU power plant conceptual study (TW2-TRP-PPCS), Final Report, FZKA 6780, Forschungszentrum Karlsruhe GmbH, Germany, 2003.
-
P. Norajitra, L. Bühler, A. Buenaventura, E. Diegele, U. Fischer, S. Gordeev, et al., Conceptual design of the dual-coolant blanket within the framework of the EU power plant conceptual study (TW2-TRP-PPCS), Final Report, FZKA 6780, Forschungszentrum Karlsruhe GmbH, Germany, 2003.
-
-
-
-
12
-
-
56049114916
-
Engineering design and analysis of the ARIES-CS power plant
-
Raffray A.R., El-Guebaly L., Malang S., Wang X.R., Bromberg L., Ihli T., et al. Engineering design and analysis of the ARIES-CS power plant. Fusion Sci. Technol. 54 (2008) 725-746
-
(2008)
Fusion Sci. Technol.
, vol.54
, pp. 725-746
-
-
Raffray, A.R.1
El-Guebaly, L.2
Malang, S.3
Wang, X.R.4
Bromberg, L.5
Ihli, T.6
-
13
-
-
31744433642
-
An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design
-
Wong C.P.C., Malang S., Sawan M., Dagher M., Smolentsev S., Merrill B., et al. An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design. Fusion Eng. Des. 81 1-7 (2006) 461-467
-
(2006)
Fusion Eng. Des.
, vol.81
, Issue.1-7
, pp. 461-467
-
-
Wong, C.P.C.1
Malang, S.2
Sawan, M.3
Dagher, M.4
Smolentsev, S.5
Merrill, B.6
-
14
-
-
33845982573
-
Conceptual design activities of FDS series fusion power plants in China
-
FDS teams
-
Wu Y., and FDS teams. Conceptual design activities of FDS series fusion power plants in China. Fusion Eng. Des. 81 (2006) 2713-2718
-
(2006)
Fusion Eng. Des.
, vol.81
, pp. 2713-2718
-
-
Wu, Y.1
-
15
-
-
34447521803
-
Design status and development strategy of China liquid lithium-lead blankets and related material technology
-
FDS teams
-
Wu Y., and FDS teams. Design status and development strategy of China liquid lithium-lead blankets and related material technology. J. Nucl. Mater. 367-370 (2007) 1410-1415
-
(2007)
J. Nucl. Mater.
, vol.367-370
, pp. 1410-1415
-
-
Wu, Y.1
-
17
-
-
56949089570
-
Structural design and analysis of dual-cooled lithium-lead blanket module for the fusion power reactor FDS-II
-
Liu Song-lin, Wang Wei-hua, Long Peng-cheng, and Wu Yi-can. Structural design and analysis of dual-cooled lithium-lead blanket module for the fusion power reactor FDS-II. Chin. J. Nucl. Sci. Eng. 25 1 (2005) 91-96
-
(2005)
Chin. J. Nucl. Sci. Eng.
, vol.25
, Issue.1
, pp. 91-96
-
-
Liu Song-lin1
Wang Wei-hua2
Long Peng-cheng3
Wu Yi-can4
-
18
-
-
34447562626
-
Progress in development of China low activation martensitic steel for fusion application
-
Huang Q., Li C., Li Y., Chen M., Zhang M., Peng L., et al. Progress in development of China low activation martensitic steel for fusion application. J. Nucl. Mater. 367-370 (2007) 142-146
-
(2007)
J. Nucl. Mater.
, vol.367-370
, pp. 142-146
-
-
Huang, Q.1
Li, C.2
Li, Y.3
Chen, M.4
Zhang, M.5
Peng, L.6
-
19
-
-
34948855740
-
Design concept and testing strategy of a dual functional lithium lead test blanket module for ITER and EAST
-
Wu Y., and FDS team. Design concept and testing strategy of a dual functional lithium lead test blanket module for ITER and EAST. Nucl. Fusion 47 (2007) 1-7
-
(2007)
Nucl. Fusion
, vol.47
, pp. 1-7
-
-
Wu, Y.1
FDS team2
-
20
-
-
34948907838
-
Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER
-
FDS team
-
Wu Y., and FDS team. Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER. Fusion Eng. Des. 82 (2007) 1893-1903
-
(2007)
Fusion Eng. Des.
, vol.82
, pp. 1893-1903
-
-
Wu, Y.1
-
22
-
-
56949089715
-
Progress in conceptual study of China fusion-based hydrogen production reactor
-
Vienna, Austria
-
Liu S., Wu Y., Chen H., Zheng S., and Bai Y. Progress in conceptual study of China fusion-based hydrogen production reactor. Reported in the 2nd IAEA Technical Meeting on First Generation of Fusion Power Plants, June 20-22. Vienna, Austria (2007)
-
(2007)
Reported in the 2nd IAEA Technical Meeting on First Generation of Fusion Power Plants, June 20-22
-
-
Liu, S.1
Wu, Y.2
Chen, H.3
Zheng, S.4
Bai, Y.5
-
23
-
-
0032475143
-
Design requirements for SiC/SiC composites structural material in fusion power reactor blankets
-
Giancarli L., Bonal J.P., Caso A., Le Marois G., Morley N.B., and Salavy J.F. Design requirements for SiC/SiC composites structural material in fusion power reactor blankets,. Fusion Eng. Des. 41 1-4 (September 1) (1998) 165-171
-
(1998)
Fusion Eng. Des.
, vol.41
, Issue.1-4 September 1
, pp. 165-171
-
-
Giancarli, L.1
Bonal, J.P.2
Caso, A.3
Le Marois, G.4
Morley, N.B.5
Salavy, J.F.6
-
24
-
-
3343004670
-
High performance blanket for ARIES-AT power plant
-
Raffray A.R., El-Guebaly L., Gordeev S., Malang S., Mogahed E., Najmabadi F., Sviatoslavsky I., Sze D.K., Tillack M.S., Wang X., and ARIES Team. High performance blanket for ARIES-AT power plant. Fusion Eng. Des. 58-59 (2001) 549-553
-
(2001)
Fusion Eng. Des.
, vol.58-59
, pp. 549-553
-
-
Raffray, A.R.1
El-Guebaly, L.2
Gordeev, S.3
Malang, S.4
Mogahed, E.5
Najmabadi, F.6
Sviatoslavsky, I.7
Sze, D.K.8
Tillack, M.S.9
Wang, X.10
ARIES Team11
-
25
-
-
0041830471
-
In-vessel component design for a self-cooled lithium-lead fusion reactor
-
Giancarli L., Bühler L., Fischer U., Enderle R., Maisonnier D., Pascal C., Pereslavtsev P., Poitevin Y., Portone A., Sardain P., Szczepanski J., and Ward D. In-vessel component design for a self-cooled lithium-lead fusion reactor. Fus. Eng. Des. 69 (2003) 763-768
-
(2003)
Fus. Eng. Des.
, vol.69
, pp. 763-768
-
-
Giancarli, L.1
Bühler, L.2
Fischer, U.3
Enderle, R.4
Maisonnier, D.5
Pascal, C.6
Pereslavtsev, P.7
Poitevin, Y.8
Portone, A.9
Sardain, P.10
Szczepanski, J.11
Ward, D.12
-
27
-
-
0029633960
-
Blanket and divertor design for force free helical reactor (FFHR)
-
Sagara A., Motojima O., Watanabe K., Imagawa S., Yamanishi H., Mitarai O., et al. Blanket and divertor design for force free helical reactor (FFHR). Fusion Eng. Des. 29 (1995) 51-56
-
(1995)
Fusion Eng. Des.
, vol.29
, pp. 51-56
-
-
Sagara, A.1
Motojima, O.2
Watanabe, K.3
Imagawa, S.4
Yamanishi, H.5
Mitarai, O.6
-
28
-
-
0343725660
-
On the exploration of innovative concepts for fusion chamber technology
-
Abdou M.A., Ying A., Morley N., Gulec K., Smolentsev S., Kotschenreuther M., et al. On the exploration of innovative concepts for fusion chamber technology. Fusion Eng. Des. 54 (2001) 181-247
-
(2001)
Fusion Eng. Des.
, vol.54
, pp. 181-247
-
-
Abdou, M.A.1
Ying, A.2
Morley, N.3
Gulec, K.4
Smolentsev, S.5
Kotschenreuther, M.6
-
29
-
-
7444233282
-
Molten salt self-cooled solid first wall and blanket design based on advanced ferritic steel
-
Wong C.P.C., Malang S., Sawan M., Sviatoslavsky I., Mogahed E., Smolentsev S., et al. Molten salt self-cooled solid first wall and blanket design based on advanced ferritic steel. Fusion Eng. Des. 72 1-3 (2004) 245-275
-
(2004)
Fusion Eng. Des.
, vol.72
, Issue.1-3
, pp. 245-275
-
-
Wong, C.P.C.1
Malang, S.2
Sawan, M.3
Sviatoslavsky, I.4
Mogahed, E.5
Smolentsev, S.6
-
30
-
-
24344493031
-
Improved structure and long-life blanket concepts for heliotron reactors
-
Sagara A., Imagawa S., Mitarai O., Dolan T., Tanaka T., Kubota Y., et al. Improved structure and long-life blanket concepts for heliotron reactors. Nucl. Fusion 45 (2005) 258-263
-
(2005)
Nucl. Fusion
, vol.45
, pp. 258-263
-
-
Sagara, A.1
Imagawa, S.2
Mitarai, O.3
Dolan, T.4
Tanaka, T.5
Kubota, Y.6
-
31
-
-
35448978690
-
Heat transfer performance for high Prandtl and high temperature molten salt flow in sphere-packed pipes
-
Satoh T., Yuki K., Chiba S., Hashizume H., and Sagara A. Heat transfer performance for high Prandtl and high temperature molten salt flow in sphere-packed pipes. Fusion Sci. Technol. 52 (2007) 618-624
-
(2007)
Fusion Sci. Technol.
, vol.52
, pp. 618-624
-
-
Satoh, T.1
Yuki, K.2
Chiba, S.3
Hashizume, H.4
Sagara, A.5
-
32
-
-
35548960482
-
Recovery of Tritium from Flibe Blanket in Fusion Reactor
-
Fukada S., Katayama K., Terai T., and Sagara A. Recovery of Tritium from Flibe Blanket in Fusion Reactor. Fusion Sci. Technol. 52 3 (2007) 677-681
-
(2007)
Fusion Sci. Technol.
, vol.52
, Issue.3
, pp. 677-681
-
-
Fukada, S.1
Katayama, K.2
Terai, T.3
Sagara, A.4
-
33
-
-
17544382521
-
Innovative liquid breeder blanket design activities in Japan
-
Sagara A., Tanaka T., Muroga T., Hashizume H., Kunugi T., Fukada S., et al. Innovative liquid breeder blanket design activities in Japan. Fusion Sci. Technol. 47 (2005) 524-529
-
(2005)
Fusion Sci. Technol.
, vol.47
, pp. 524-529
-
-
Sagara, A.1
Tanaka, T.2
Muroga, T.3
Hashizume, H.4
Kunugi, T.5
Fukada, S.6
-
34
-
-
32544447760
-
Blanket neutronics of Li/vanadium-alloy and Flibe/vanadium-alloy systems for FFHR
-
Muroga T., Tanaka T., and Sagara A. Blanket neutronics of Li/vanadium-alloy and Flibe/vanadium-alloy systems for FFHR. Fusion Eng. Des. 81 (2006) 1203-1209
-
(2006)
Fusion Eng. Des.
, vol.81
, pp. 1203-1209
-
-
Muroga, T.1
Tanaka, T.2
Sagara, A.3
-
35
-
-
0034316626
-
EVOLVE-an advanced first wall/blanket system
-
Mattas R.F., Malang S., Khater H., Majumdar S., Mogahed E., Nelson B., et al. EVOLVE-an advanced first wall/blanket system. Fusion Eng. Des. 49-50 (2000) 613-620
-
(2000)
Fusion Eng. Des.
, vol.49-50
, pp. 613-620
-
-
Mattas, R.F.1
Malang, S.2
Khater, H.3
Majumdar, S.4
Mogahed, E.5
Nelson, B.6
-
36
-
-
0036864636
-
Range of blanket concepts from near term solutions to advanced concepts
-
Malang S., Raffray A.R., Sagara A., and Ying A. Range of blanket concepts from near term solutions to advanced concepts. Fusion Eng. Des. 61-62 (2002) 295-306
-
(2002)
Fusion Eng. Des.
, vol.61-62
, pp. 295-306
-
-
Malang, S.1
Raffray, A.R.2
Sagara, A.3
Ying, A.4
|