Global depletion analysis of Korean helium cooled solid breeder TBM model for demo fusion reactor

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The Korean HCSB (helium cooled solid breeder) TBM (test blanket module) is proposed with its specific compositions of lithium ceramic, beryllium and graphite in pebble form. In the Korean HCSB TBM, the amount of beryllium is reduced and the reduction is replaced by graphite for a neutron reflector, while tritium breeding ratio (TBR) remains almost unchanged with relatively low Li(6) enrichment of similar to 40%. However, the previous Korean HCSB was designed based on the LOCAL assumption, in which the surroundings are assumed by the reflective boundary condition. In this research, we establish a simple GLOBAL neutronics model based on demo fusion reactor and perform neutronics analyses including depletion (transmutation) calculation during 100 EFPDs (effective full power days) using the modified MONTEBURNS code. (C) 2010 Elsevier B.V. All rights reserved.
Publisher
ELSEVIER SCIENCE SA
Issue Date
2010-12
Language
English
Article Type
Article; Proceedings Paper
Keywords

TEST BLANKET MODULE; DESIGN; ITER

Citation

FUSION ENGINEERING AND DESIGN, v.85, no.10-12, pp.2222 - 2226

ISSN
0920-3796
URI
http://hdl.handle.net/10203/100575
Appears in Collection
NE-Journal Papers(저널논문)
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