Tritium removal by Y hot trap for purification of IFMIF Li target
Tritium removal by Y hot trap for purification of IFMIF Li target
复制标题
Y 热阱除氚纯化 IFMIF 锂靶材
DOI：
10.1016/j.fusengdes.2009.06.002
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发表时间：
2010
影响因子：
1.7
通讯作者：
H. Nakamura
中科院分区：
文献类型：
--
作者：
Y. Edao;S. Fukada;S. Yamaguchi;Y. Wu;H. Nakamura
预计将使用锂作为国际聚变材料辐照设施（IFMIF）的流动靶，以产生高强度中子。副产物的氚（T）通过放置在流动的Li靶的旁路位置中的Y热阱去除。由于氢同位素的平衡压力极低，因此氢同位素的去除率会受到溶解在Li中的其他杂质如N、C和O的影响。在本研究中，实验研究了三种不同方法或条件下Li中H同位素的去除率：（i）在静态Li+Y系统中，在Ar吹扫中供应低浓度H2，（ii）在静态Li+Y体系中，中子辐照后T放射性的变化;（iii）在搅拌Li+ Y体系中，Y系统用低浓度H2供应Ar吹扫。在500°C下接触100 h后，Li-Y界面没有腐蚀现象。目前的结果被扩展到设计一个Y热阱的IFMIF-EVEDA锂回路，以消除H同位素小于指定的浓度。
The use of Li is expected for a flowing target in the International Fusion Materials Irradiation Facility (IFMIF) for high-intensity neutron generation. Tritium (T) of by-product is removed by a Y hot trap placed in a by-path position of the flowing Li target. Since the equilibrium pressure of hydrogen isotopes is extremely low, the removal rate of H isotopes is affected by coexisting other impurities such as N, C and O dissolved in Li. In the present study, the removal rate of H isotopes in Li is experimentally investigated under the three different methods or conditions: (i) measuring gravimetrically in a static Li+Y system with the supply of low-concentration H2in Ar purge, (ii) counting the change of T radioactivity in a static Li+Y system after neutron irradiation and (iii) measuring the change of the H2concentration in a stirred Li+Y system with the supply of low-concentration H2in Ar purge. There was no corrosive action in the Li–Y interface observed after contact at 500°C for 100h. The present results are extended to design a Y hot trap for the IFMIF–EVEDA Li loop in order to remove H isotopes less than a specified concentration.
DOI：
--
发表时间：
2007
期刊：
Fusion Engineering and Design 82
影响因子：
--
作者：
S.Fukada;M.Kinoshita;Y.Maeda;T.Muroga
通讯作者：
T.Muroga