Review of blanket designs for advanced fusion reactors

被引:151
作者
Ihli, T. [1 ]
Basu, T. K. [2 ]
Giancarli, L. M. [3 ]
Konishi, S. [4 ]
Malang, S.
Najmabadi, F. [5 ]
Nishio, S. [6 ]
Raffray, A. R. [5 ]
Rao, C. V. S. [7 ]
Sagara, A. [8 ]
Wu, Y. [9 ]
机构
[1] Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany
[2] Bhabha Atom Res Ctr, Bombay 400085, Maharashtra, India
[3] CEA Saclay, F-91191 Gif Sur Yvette, France
[4] Kyoto Univ, Inst Adv Energy, Kyoto 6110011, Japan
[5] Univ Calif San Diego, La Jolla, CA 90093 USA
[6] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan
[7] Inst Plasma Res, Gandhinagar, Gujarat, India
[8] Natl Inst Nat Sci, Natl Inst Fus Sci, Toki, Gifu 5095292, Japan
[9] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
关键词
Advanced blanket; HCPB; DCLL; SCLL; Flibe; EVOLVE; Review; Helium; Lead lithium;
D O I
10.1016/j.fusengdes.2008.07.039
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 [核科学与技术]; 082701 [核能科学与工程];
摘要
The dominating fraction of the power generated by fusion in the reactor is captured by neutron moderation in the blanket surrounding the plasma. From this, the efficiency of the fusion plant is predominated by the technologies applied to make electricity or hydrogen from the neutrons. The main blanket concepts addressed in this paper are advanced ceramic breeder concepts, dual coolant blankets as well as self-cooled liquid metal and Flibe blankets. Two important questions that are addressed are: (i) Can we draw a bottom line conclusion on the most promising concept(s)? (ii) What are the common issues to be resolved independently from individual design and layout proposals to define a feasible route towards advanced fusion reactors? For ceramic breeder concepts, a key issue in the long term could be the limitation of beryllium as the considered multiplier in terms of world sources and achievable temperature levels. For liquid metal blankets, attractive long-term visions have been developed but major technological challenges also exist for the in-vessel blanket technology and the corresponding sub-systems. The paper proposes a strategic conclusion derived from the review of blanket designs for advanced fusion reactors. (c) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:912 / 919
页数:8
相关论文
共 36 条
[1]
On the exploration of innovative concepts for fusion chamber technology [J].
Abdou, MA ;
Ying, A ;
Morley, N ;
Gulec, K ;
Smolentsev, S ;
Kotschenreuther, M ;
Malang, S ;
Zinkle, S ;
Rognlien, T ;
Fogarty, P ;
Nelson, B ;
Nygren, R ;
McCarthy, K ;
Youssef, MZ ;
Ghoniem, N ;
Sze, D ;
Wong, C ;
Sawan, M ;
Khater, H ;
Woolley, R ;
Mattas, R ;
Moir, R ;
Sharafat, S ;
Brooks, J ;
Hassanein, A ;
Petti, D ;
Tillack, M ;
Ulrickson, M ;
Uchimoto, T .
FUSION ENGINEERING AND DESIGN, 2001, 54 (02) :181-247
[2]
Advanced helium cooled pebble bed blanket with SiCf/SiC as structural material [J].
Boccaccini, LV ;
Fischer, U ;
Gordeev, S ;
Malang, S .
FUSION ENGINEERING AND DESIGN, 2000, 49-50 :491-497
[3]
CHEN H, 2007, P 8 INT S FUS NUCL T
[4]
DALLEDONNE M, 1995, FUSION ENG DES, V27, P319
[5]
Recovery of tritium from flibe blanket in fusion reactor [J].
Fukada, S. ;
Katayama, K. ;
Terai, T. ;
Sagara, A. .
FUSION SCIENCE AND TECHNOLOGY, 2007, 52 (03) :677-681
[6]
In-vessel component designs for a self-cooled lithium-lead fusion reactor [J].
Giancarli, L ;
Bühler, L ;
Fischer, U ;
Enderle, R ;
Maisonnier, D ;
Pascal, C ;
Pereslavtsev, P ;
Poitevin, Y ;
Portone, A ;
Sardain, P ;
Szczepanski, J ;
Ward, D .
FUSION ENGINEERING AND DESIGN, 2003, 69 (1-4) :763-768
[7]
Progress in blanket designs using SiCf/SiC composites [J].
Giancarli, L ;
Golfier, H ;
Nishio, S ;
Raffray, R ;
Wong, C ;
Yamada, R .
FUSION ENGINEERING AND DESIGN, 2002, 61-62 :307-318
[8]
Design requirements for SiC/SiC composites structural material in fusion power reactor blankets [J].
Giancarli, L ;
Bonal, JP ;
Caso, A ;
Le Marois, G ;
Morley, NB ;
Salavy, JF .
FUSION ENGINEERING AND DESIGN, 1998, 41 :165-171
[9]
Progress in development of China Low Activation Martensitic Steel for fusion application [J].
Huang, Q. ;
Li, C. ;
Li, Y. ;
Chen, M. ;
Zhang, M. ;
Peng, L. ;
Zhu, Z. ;
Song, Y. ;
Gao, S. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 367 :142-146
[10]
Recent progress in DEMO fusion core engineering: Improved segmentation, maintenance and blanket concepts [J].
Ihli, T. ;
Boccaccini, L. V. ;
Janeschitz, G. ;
Koehly, C. ;
Maisonnier, D. ;
Nagy, D. ;
Polix, C. ;
Rey, J. ;
Sardain, P. .
FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) :2705-2712