TRANSPORT OF URANIUM THROUGH A CRACKED CLAY BARRIER

被引:6
作者
GARISTO, NC
GARISTO, F
机构
[1] Atomic Energy of Canada Limited Whiteshell Nuclear Research Establishment Pinawa
关键词
D O I
10.1016/0306-4549(90)90052-F
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
Bentonite-based clays are proposed as a barrier to radionuclide migration in the geological disposal of used UO2 fuel. There is some evidence, however, that this buffer may be susceptible to cracking. Therefore, we have investigated the effect of cracking on the transport of dissolved uranium through the buffer using numerical models. The results indicate that, for swept-away boundary conditions at the rock/buffer interface, the total uranium flux through a cracked buffer is, as expected, greater than through an uncracked buffer. The effect of the cracks is strongly dependent on the ratio D DB, where D and DB are the pore-water and the buffer diffusion coefficients, respectively. In contrast, for semi-impermeable boundary conditions at the rock/buffer interface, the effect of the cracks on the total uranium flux is relatively small. © 1990.
引用
收藏
页码:183 / 193
页数:11
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