An investigation into dissolution rate of spent nuclear fuel in aqueous reprocessing

被引:12
作者
Mineo, H [1 ]
Isogai, H [1 ]
Morita, Y [1 ]
Uchiyama, G [1 ]
机构
[1] Japan Atom Energy Res Inst, Tokai, Ibaraki 3191195, Japan
关键词
reprocessing; spent fuel; LWR type reactors; FBR type reactors; uranium dioxide; nitric acid; crack; burnup; rod power; dissolution rate;
D O I
10.3327/jnst.41.126
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
A simple equation was proposed for the dissolution rate of spent LWR fuel, of which the change in the dissolution area was estimated by taking into account of the area of the cracks in the pellet caused by thermal stress during irradiation. The applicability of proposed equation was examined using LWR spent fuel dissolution test results in the present study as well as the results obtained by other workers. The equation showed good agreements with the dissolution test results obtained from spent fuel pellets and pulverized spent fuel. It was indicated that the proposed equation was simple and would be useful for the prediction of dissolution of spent LWR fuels.
引用
收藏
页码:126 / 134
页数:9
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