Uranium processing during the treatment of sodium-bonded spent nuclear fuel

被引：16

作者：

Westphal, BR ^{[1
]}

Mariani, RD ^{[1
]}

机构：

[1] Argonne Natl Lab, Nucl Technol Dept, Idaho Falls, ID 83403 USA

来源：

JOM-JOURNAL OF THE MINERALS METALS & MATERIALS SOCIETY | 2000年 / 52卷 / 09期

关键词：

Uranium; Fuel Assembly; Demonstration Program; Waste Form; Ceramic Waste;

D O I：

10.1007/s11837-000-0182-1

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Several key technical areas have been developed during a demonstration program at Argonne National Laboratory to advance the electrometallurgical treatment of spent nuclear fuel, including equipment operating conditions, uranium-product purity and recovery, and processing rates. Operating conditions for three integral processing steps were optimized based on minimizing the impurities to the final uranium product while meeting program goals for processing rates. The overall recovery of uranium during the process steps was influenced by process conditions as well as the production; rates set forth for the demonstration program.

引用

页码：21 / 25

页数：5

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