The European test blanket module systems:: Design and integration in ITER

被引:29
|
作者
Boccaccini, LV
Salavy, JF
Lässer, R
Puma, AL
Meyder, R
Neuberger, H
Poitevin, Y
Rampal, G
机构
[1] Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany
[2] CEA Saclay, Direct Energie Nucl, F-91191 Gif Sur Yvette, France
[3] EFDA Garching CSU, D-85748 Garching, Germany
关键词
test blanket; ITER; liquid breeder; solid breeder; helium cooling;
D O I
10.1016/j.fusengdes.2005.09.008
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The European Union proposes two different concepts of helium-cooled blanket for testing in ITER, one with ceramic breeder and beryllium, the second with lithium lead as breeder and multiplier. Test blanket modules (TBM) for both blanket concepts and their auxiliary systems have being designed in the last 2 years; this paper presents the status of this work as reached in January 2005. In particular the design of the two TBMs is discussed pointing out the common original architecture and the differences in the design choices due to different functionality, test necessities and adaptation to the ITER boundary conditions. The integration of these systems in ITER is presented in the second part of this paper. A new proposal for the integration of the TBMs inside the port plug, their replacement in the hot cell and the arrangement of the auxiliary systems in the ITER buildings is discussed. (c) 2005 Elsevier B.V. All rights reserved.
引用
收藏
页码:407 / 414
页数:8
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