Removal of Uranium from Plutonium Solutions by Anion Exchange.

Rudisill, T. S. ; Duffey, J. M.

Technical Information Center Oak Ridge Tennessee

关键词: Materials recovery;    Anion exchange;    Uranium;    Capacity;    Depleted uranium;   

RP-ID  :  DE2004799696

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

The anion exchange capacity in the HB-Line Phase II Facility will be used to purify plutonium solutions potentially containing significant quantities of depleted uranium. Following purification, the plutonium will be precipitated as an oxalate and calcined to plutonium oxide (PuO2) for storage until final disposition.