FY-15 Progress Report on Cleanup of irradiated SHINE Target Solutions Containing 140g-U/L Uranyl Sulfate

Bennett, Megan E.¹  Bowers, Delbert L.¹  Vandegrift, George F.¹ 

[1]Argonne National Lab. (ANL), Argonne, IL (United States)

关键词: SOLUTIONS;    URANYL SULFATES;    URANIUM;    EXTRACTION;    REPROCESSING;    MATERIALS RECOVERY;    PROGRESS REPORT;    URANYL NITRATES;    BARIUM;   

DOI  :  10.2172/1234218
RP-ID  :  ANL/NE--15/38
PID  :  OSTI ID: 1234218
Others  :  Other: 123419
Others  :  TRN: US1600213

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

During FY 2012 and 2013, a process was developed to convert the SHINE Target Solution (STS) of irradiated uranyl sulfate (140 g U/L) to uranyl nitrate. This process is necessary so that the uranium solution can be processed by the UREX (Uranium Extraction) separation process, which will remove impurities from the uranium so that it can be recycled. The uranyl sulfate solution must contain <0.02 M SO₄^2- so that the uranium will be extractable into the UREXsolvent. In addition, it is desired that the barium content be below 0.0007 M, as this is the limit in the Resource Conservation and Recovery Act (RCRA).