Status of engineering design of liquid lithium target in IFMIF-EVEDA

被引:25
|
作者
Nakamura, Hiroo [1 ]
Agostini, Pietro
Ara, Kuniaki
Fukada, Satoshi
Furuya, Kazuyuki [2 ]
Garin, Pascal
Gessi, Alessandro
Giusti, David
Groeschel, Friedrich
Horiike, Hiroshi [3 ]
Ida, Mizuho
Kanenmura, Takuji [3 ]
Kondo, Hiroo
Loginov, Nikolai [4 ]
Micciche, Gioacchino
Miyashita, Makoto
Nitti, F. S.
Suzuki, Akihiro [5 ]
Terai, Takayliki [5 ]
Watanabe, Kazuhiro
Yagi, Juro [5 ]
Yoshida, Eiichi
Mikheyev, A. [4 ]
机构
[1] Japan Atom Energy Agcy, IFMIF Dev Grp, Tokai Res & Dev Ctr, Tokai, Ibaraki 3191195, Japan
[2] Hachinohe Inst Technol, Hachinohe, Aomori, Japan
[3] Osaka Univ, Suita, Osaka 565, Japan
[4] IPPE Obninsk, Obninsk, Russia
[5] Univ Tokyo, Tokyo 1138654, Japan
关键词
IFMIF; Neutron source; Liquid lithium; Target; F82H; EUROFER; Remote handling; Radiation damage; DBTT; Design;
D O I
10.1016/j.fusengdes.2009.02.019
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
In International Fusion Materials Irradiation Facility (IFMIF), intense neutron flux (4.5 x 10(17) n/m(2) s) with a peak energy of 14 MeV are produced by means of two deuteron beams wit It a total Current of 250 mA and maximum energy of 40 MeV that strike a liquid Li target circulating in a Li loop. Major design requirement is to provide a stable Li jet at a speed of 10-20 m/s with a surface wave amplitude on the Li flow less than 1 mm for handling of an averaged heat flux Of 1 GW/m(2) under a continuous 10 MW deuterium beam deposition. The target system consists of a target assembly. a replaceable back-plate, a Li main loop and a Li purification loop. In July 2007. Engineering Validation and Engineering Design Activities (EVEDA) started under Broader Approach. In this paper, status of the engineering design of the IFMIF Li target system performed in 2007/2008 is described. The future EVEDA tasks to develop the target system are also summarized. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:252 / 258
页数:7
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