...
首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Separation of actinides from irradiated An-Zr based fuel by electrorefining on solid aluminium cathodes in molten LiCl-KCl
【24h】

Separation of actinides from irradiated An-Zr based fuel by electrorefining on solid aluminium cathodes in molten LiCl-KCl

机译:通过在熔融的LiCl-KCl中的固态铝阴极上进行电精炼来从辐照的An-Zr基燃料中分离act系元素

获取原文
获取原文并翻译 | 示例
   

获取外文期刊封面封底 >>

       

摘要

An electrorefining process for metallic spent nuclear fuel treatment is being investigated in ITU. Solid aluminium cathodes are used for homogeneous recovery of all actinides within the process carried out in molten LiCl-KCl eutectic salt at a temperature of 500 degrees C. As the selectivity, efficiency and performance of solid Al has been already shown using un-irradiated An-Zr alloy based test fuels, the present work was focused on laboratory-scale demonstration of the process using irradiated METAPHIX-1 fuel composed of U-67-Pu-19-Zr-10-MA(2)-RE2 (wt.%, MA = Np, Am, Cm, RE = Nd, Ce, Gd, Y). Different electrorefining techniques, conditions and cathode geometries were used during the experiment yielding evaluation of separation factors, kinetic parameters of actinide-aluminium alloy formation, process efficiency and macro-structure characterisation of the deposits. The results confirmed an excellent separation and very high efficiency of the electrorefining process using solid Al cathodes. (C) 2015 The Authors. Published by Elsevier B.V.
机译:国际电联正在研究用于处理乏金属核燃料的电精炼工艺。固态铝阴极用于在熔融LiCl-KCl共晶盐中在500摄氏度的温度下进行的过程中所有act系元素的均相回收。由于使用未辐照的An,已经显示出固态Al的选择性,效率和性能-Zr合金测试燃料,目前的工作集中在实验室规模的演示过程中,该过程使用由U-67-Pu-19-Zr-10-MA(2)-RE2(wt。% ,MA = Np,Am,Cm,RE = Nd,Ce,Gd,Y)。实验过程中使用了不同的电精炼技术,条件和阴极几何形状,以评估分离因子,of系元素-铝合金形成的动力学参数,工艺效率和沉积物的宏观结构表征。结果证实了使用固体铝阴极的电精炼过程具有出色的分离效果和极高的效率。 (C)2015作者。由Elsevier B.V.发布

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号