Effect of sweep gas species on tritium release behavior from lithium titanate packed bed during 14 MeV neutron irradiation

被引:18
作者
Kawamura, Yoshinori [1 ]
Ochiai, Kentaro [1 ]
Hoshino, Tsuyoshi [1 ]
Kondo, Keitaro [1 ]
Iwai, Yasunori [1 ]
Kobayashi, Kazuhiro [1 ]
Nakamichi, Masaru [1 ]
Konno, Chikara [1 ]
Yamanishi, Toshihiko [1 ]
Hayashi, Takumi [1 ]
Akiba, Masato [1 ]
机构
[1] Japan Atom Energy Agcy, Tokyo, Japan
关键词
Breeder blanket; Tritium; Fusion neutron; Ceramic breeder; Beryllium; Sweep gas; CERAMIC BREEDER MATERIALS; PURGE GAS; HYDROGEN ADDITION; LI2TIO3; WATER;
D O I
10.1016/j.fusengdes.2012.02.125
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 a fusion reactor, the prediction of tritium release behavior from breeder blanket is important to design the tritium recovery system, but the amount of tritium generated is necessary information to do that. Hence, tritium generation and recovery studies on lithium ceramics packed bed have been started by using fusion neutron source (FNS) in Japan Atomic Energy Agency (JAEA). Lithium titanate (Li2TiO3) was selected as tritium breeding material, and its packed bed was enclosed by the beryllium blocks, and was kept at certain temperature during fusion neutron irradiation. During irradiation, the packed bed was purged with the sweep gas continuously, and tritium released was trapped in each gas absorber selectively by chemical form. In this work, the effect of sweep gas species on tritium release behavior was investigated. In the case of sweep by helium with 1% of hydrogen, tritium in water form was released sensitively corresponding to the irradiation. This is due to existence of the water vapor in the sweep gas. On the other hand, in the case of sweep by helium without water vapor, tritium in gaseous form was released first, and release of tritium in water form was delayed from gaseous tritium and was gradually increased. (C) 2012 Elsevier B.V. All rights reserved.
引用
收藏
页码:1253 / 1257
页数:5
相关论文
共 13 条
[1]   Surface desorption and bulk diffusion models of tritium release from Li2TiO3 and Li2ZrO3 pebbles [J].
Avila, R. E. ;
Pena, L. A. ;
Jimenez, J. C. .
JOURNAL OF NUCLEAR MATERIALS, 2010, 405 (03) :244-251
[2]  
Conrad J., 1991, J NUCL MATER, V179-181, P1158
[3]   Formation of water in lithium ceramics bed at hydrogen addition to purge gas [J].
Kawamura, Y ;
Nishikama, M ;
Shiraishi, T ;
Okuno, K .
JOURNAL OF NUCLEAR MATERIALS, 1996, 230 (03) :287-294
[4]   Tritium diffusivity in crystal grain of Li2TiO3 and tritium release behavior under several purge gas conditions [J].
Kinjyo, T. ;
Nishikawa, M. ;
Enoeda, M. ;
Fukada, S. .
FUSION ENGINEERING AND DESIGN, 2008, 83 (04) :580-587
[5]   Tritium release behavior from Li4SiO4 [J].
Kinjyo, T ;
Nishikawa, M .
FUSION SCIENCE AND TECHNOLOGY, 2004, 46 (04) :561-570
[6]   Comparison of modelling of tritium release from ceramic breeder materials [J].
Munakata, K ;
Yokoyama, Y ;
Baba, A ;
Penzhorn, RD ;
Oyaidzu, M ;
Okuno, K .
FUSION ENGINEERING AND DESIGN, 2005, 75-79 :673-678
[7]   Release behavior of bred tritium from LiAlO2 [J].
Nishikawa, M ;
Kinjyo, T ;
Ishizaka, T ;
Beloglazov, S ;
Takeishi, T ;
Enoeda, M ;
Tanifuji, T .
JOURNAL OF NUCLEAR MATERIALS, 2004, 335 (01) :70-76
[8]   Chemical form of tritium released from solid breeder materials [J].
Nishikawa, M ;
Kinjyo, T ;
Nishida, Y .
JOURNAL OF NUCLEAR MATERIALS, 2004, 325 (2-3) :87-93
[9]   FORMATION OF WATER IN A LI2O BED AT HYDROGEN ADDITION TO PURGE GAS [J].
NISHIKAWA, M ;
KAWAMURA, Y ;
MUNAKATA, K ;
MATSUMOTO, H .
JOURNAL OF NUCLEAR MATERIALS, 1990, 174 (01) :121-123
[10]  
Ochiai K., 2010, 23 IAEA FUS EN C DAE