Removal of Uranium from Plutonium Solutions by Anion Exchange

Rudisill, T.S.

Savannah River Site (S.C.)

关键词: Removal;    Storage;    Capacity;    Depleted Uranium;    Oxalates;   

DOI  :  10.2172/799696
RP-ID  :  WSRC-TR-2002-00097
RP-ID  :  AC09-96SR18500
RP-ID  :  799696

美国|英语

来源: UNT Digital 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.