Separation and recovery study of uranium from spent NaF (fillers)

被引：13

作者：

Amamoto, I ^{[1
]}

Terai, T

Oobayashi, H

Fujita, R

机构：

[1] Univ Tokyo, Dept Quantum Engn & Syst Sci, Sch Engn, Tokyo 1138656, Japan

[2] Japan Nucl Cycle Dev Inst, Ningyo Toge Ennvironm Engn Ctr, Okayama 7080698, Japan

[3] Japan Nucl Cycle Dev Inst, Ooarai Engn Ctr, Ibaraki 3111393, Japan

[4] Toshiba Co Ltd, Nucl Engn Lab, Kawasaki, Kanagawa 2100862, Japan

来源：

JOURNAL OF PHYSICS AND CHEMISTRY OF SOLIDS | 2005年 / 66卷 / 2-4期

关键词：

D O I：

10.1016/j.jpcs.2004.07.019

中图分类号：

O6 [化学];

学科分类号：

0703 ;

摘要：

The molten salt technique is considered to be a feasible technique applicable for the removal of uranium from the spent NaF (fillers). Simple spent NaF or NaF with NaCl, i.e. mixed salt, was used as an electrolyte and the uranium concentrations in the bath, pre-treatment condition, electrolytic temperature, current density, etc. were given as parameters in this experiment. Results from the fundamental experiments showed the potential applicability of the molten salt technique for the removal of uranium from spent NaF. (c) 2004 Published by Elsevier Ltd.

引用

页码：602 / 607

页数：6