On the development of a distillation process for the electrometallurgical treatment of irradiated spent nuclear fuel

被引:45
作者
Westphav, Brian R. [1 ]
Marsden, Kenneth C. [1 ]
Price, John C. [1 ]
Laug, David V. [1 ]
机构
[1] Idaho Natl Lab, Idaho Falls, ID 83415 USA
关键词
vacuum distillation; actinide recovery; electrometallurgical treatment; pyroprocesssing;
D O I
10.5516/NET.2008.40.3.163
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
As part of the spent fuel treatment program at the Idaho National Laboratory, a vacuum distillation process is being employed for the recovery of actinide products following an electrorefining process. Separation of the actinide products from a molten salt electrolyte and cadmium is achieved by a batch operation called cathode processing. A cathode processor has been designed and developed to efficiently remove the process chemicals and consolidate the actinide products for further processing. This paper describes the fundamentals of cathode processing, the evolution of the equipment design, the operation and efficiency of the equipment, and recent developments at the cathode processor. In addition, challenges encountered during the processing of irradiated spent nuclear fuel in the cathode processor will be discussed.
引用
收藏
页码:163 / 174
页数:12
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