Latest design of liquid lithium target in IFMIF

被引：18
|
作者：
Nakamura, H. [1 ]
Agostini, P.
Ara, K.
Cevolani, S.
Chida, T.
Ciotti, M.
Fukada, S. [2 ]
Furuya, K.
Garin, P.
Gessii, A.
Guisti, D.
Heinzel, V.
Horiike, H. [3 ]
Ida, M.
Jitsukawa, S.
Kanemura, T. [3 ]
Kondo, H. [3 ]
Kukita, Y. [4 ]
Loesser, R. [5 ]
Matsui, H. [6 ]
Micciche, G.
Miyashita, M.
Muroga, T.
Riccardi, B. [5 ]
Simakov, S.
Stieglitz, R.
Sugimoto, M.
Suzuki, A. [7 ]
Tanaka, S. [7 ]
Terai, T. [7 ]
Yagi, J. [7 ]
Yoshida, E.
Wakai, E.
机构：
[1] Japan Atom Energy Agcy, Tokai Res & Dev Ctr, Tokai, Ibaraki 3191195, Japan
[2] Kyushu Univ, Fukuoka 812, Japan
[3] Osaka Univ, Suita, Osaka 565, Japan
[4] Nagoya Univ, Nagoya, Aichi 4648601, Japan
[5] EFDA Garching, Garching, Germany
[6] Tohoku Univ, Sendai, Miyagi 980, Japan
[7] Univ Tokyo, Tokyo 1138654, Japan
来源：
FUSION ENGINEERING AND DESIGN | 2008年 / 83卷 / 7-9期
关键词：
IFMIF; Liquid lithium target; Free surface; Cold trap; Hot trap; RAFM; Neutron irradiation; Remote handling; EVEDA;
D O I：
10.1016/j.fusengdes.2008.06.014
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：
This paper describes the latest design of liquid lithium (Li) target system in International Fusion Materials Irradiation Facility (IFMIF). IFMIF is an accelerator-driven intense neutron source for fusion reactor materials testing. Two 40 MeV deuteron beams with a total current of 250 mA strikes a liquid Li target circulating in a Li loop. The Li target is to provide a stable Li jet at a speed of 10-20 m/s to handle an averaged heat flux of 1 GW/m(2), A concaved Li flow is applied to avoid Li boiling. A cold trap and two kinds of hot trap are applied to control impurities (T, (7)Be, C, O, N) below permissible levels. A back wall made of RAFM is located in the most severe region of neutron irradiation (50 dpa/year). System availability requires more than 95% during plant lifetime. EVEDA tasks including Li loop are now being performed under the Broader Approach. (C) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码：1007 / 1014
页数：8
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