A neutronic investigation of He-cooled liquid Li-breeder blankets for fusion power reactor

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Configuration of a He-cooled liquid lithium blanket has been optimized in terms of the tritium breeding ratio (TBR) and the neutron shielding. For a model blanket, fundamental neutronic characteristics are analyzed with a Monte Carlo code. To improve the TBR, various neutron reflectors are compared, which are graphite, TiC and ZrH(2), and the optimal application of the reflector is investigated, either lumped or layered. The TBR is analyzed as a function of the Li-6 enrichment for the reflected blanket, and the results are used in determining the lifetime of a natural lithium breeder. In addition, various types of moderated shields are assessed to improve the neutron shielding performance. (c) 2005 Elsevier B.V. All rights reserved.
Publisher
ELSEVIER SCIENCE SA
Issue Date
2005-11
Language
English
Article Type
Article; Proceedings Paper
Keywords

LITHIUM

Citation

FUSION ENGINEERING AND DESIGN, v.75-79, pp.1067 - 1070

ISSN
0920-3796
DOI
10.1016/j.fusengdes.2005.06.005
URI
http://hdl.handle.net/10203/89100
Appears in Collection
NE-Journal Papers(저널논문)
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