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

被引:2
|
作者
Yun, Sunghwan [1 ]
Cho, Nam Zin [1 ]
Ahn, Mu-Young [2 ]
Cho, Seungyon [2 ]
机构
[1] Korea Adv Inst Sci & Technol, Taejon 305701, South Korea
[2] ITER Korea Natl Fus Res Inst, TBM Technol Team, Taejon 305333, South Korea
关键词
Monte Carlo; Helium cooled solid breeder (HCSB); MONTEBURNS code; Depletion calculation; TEST BLANKET MODULE; DESIGN; ITER;
D O I
10.1016/j.fusengdes.2010.08.042
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 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.
引用
收藏
页码:2222 / 2226
页数:5
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