Removal and Control of Tritium in Lithium Target for International Fusion Materials Irradiation Facility (IFMIF)
Removal and Control of Tritium in Lithium Target for International Fusion Materials Irradiation Facility (IFMIF)
复制标题
国际聚变材料辐照设施（IFMIF）锂靶中氚的去除和控制
DOI：
10.13182/fst02-a22704
复制
发表时间：
2002
影响因子：
0.9
通讯作者：
H. Takeuchi
中科院分区：
文献类型：
--
作者：
H. Nakamura;M. Ida;M. Sugimoto;T. Yutani;H. Takeuchi
本文介绍了IFMIF用液态锂靶的氚去除和控制。为了产生强流中子，将40 MeV的氘束以250 mA的电流注入到速度为20 m/s的液态Li流中。D-Li反应产生氚，产率为7 g/y。用钇吸气剂热阱除去锂中的氚，并将其控制在0.65appm以下。作为一种选择，与冷阱的沼泽方法进行了研究。
ABSTRACT This paper describes removal and control of tritium of liquid lithium (Li) target for IFMIF. To produce intense neutrons, 40 MeV deuteron beam with a current of 250 mA is injected into a liquid Li flow with a speed of 20 m/s. D-Li reaction produces tritium with a production rate of 7 g/y. Tritium in Li is removed by a hot trap with an yttrium getter and controlled less than 0.65 appm. As an option, a swamping method with a cold trap is investigated.