共 11 条
[11]
VASILYEV VG, 1986, 14TH P SOFT, P1505
IN-REACTOR TRITIUM RELEASE EXPERIMENT FROM MOLTEN LITHIUM-LEAD ALLOY (LI17PB83)
被引：13
作者：
TERAI, T
NAGAI, S
TAKAHASHI, Y
机构：
[1] Department of Nuclear Engineering, Faculty of Engineering, University of Tokyo, Bunkyo-ku, Tokyo, 113, 7-3-1, Hongo
关键词：
D O I：
10.1016/0022-3115(91)90227-X
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
An in situ tritium release experiment from molten Li17Pb83 alloy was performed under neutron irradiation at 300-700-degrees-C to investigate the chemical form and release rate of tritium. The dominant chemical form of the released tritium (> 99.9%) from fresh Li17Pb83 was the water-insoluble component (HT, T2), irrespective of the H-2 concentration in He carrier gas (0, 100, 1000, 10000 ppm). After 10 runs, however, the fraction of the water-insoluble component decreased considerably, and depended strongly upon the H-2 concentration in He carrier gas. The tritium release rate was affected by the carrier gas composition and flow mode (sweeping or bubbling). These results suggest that the tritium release is affected by a surface reaction on the molten alloy as well as diffusion and convection in the melt.
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页码：871 / 874
页数：4
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