ANODIC-DISSOLUTION OF URANIUM MONONITRIDE IN LITHIUM CHLORIDE-POTASSIUM CHLORIDE EUTECTIC MELT

被引：21

作者：

KOBAYASHI, F

OGAWA, T

AKABORI, M

KATO, Y

机构：

[1] Japan Atomic Energy Research Institute, Naka-Gun, Ibaraki, 319-11, Tokai-mura

来源：

JOURNAL OF THE AMERICAN CERAMIC SOCIETY | 1995年 / 78卷 / 08期

关键词：

D O I：

10.1111/j.1151-2916.1995.tb08657.x

中图分类号：

TQ174 [陶瓷工业]; TB3 [工程材料学];

学科分类号：

0805 ; 080502 ;

摘要：

Uranium-plutonium nitride is a candidate fuel for fast reactors, but its major drawback is C-14 formation from natural nitrogen. One would probably have to use highly N-15-enriched nitrogen. A pyrochemical process with molten-salt electrorefining has been proposed as a means to increase the nuclear proliferation resistance of the fuel cycle. Molten-salt electrorefining could also be applied to nitride fuels to make possible the recycling of N-15. The anodic dissolution behavior of UN in LiCl-KCl melt was studied to provide the basis for a feasibility study of electrorefining of irradiated nitride fuels.

引用

页码：2279 / 2281

页数：3

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