Evaluation of the Effects of Tank 50H Solids on Dissolved Uranium, Plutonium and Neptunium

Oji, L.N.

Savannah River Site (S.C.)

关键词: Removal;    Uranium;    Catalytic Effects;    Neptunium;    Oxalates;   

DOI  :  10.2172/819999
RP-ID  :  WSRC-TR-2003-00114, Rev. 1
RP-ID  :  AC09-96SR18500
RP-ID  :  819999

美国|英语

来源: UNT Digital Library

【 摘 要 】

The study of the effects of contacting a simulated salt solution spiked with uranium, plutonium, and neptunium with Tank 50H solids. General findings include: There is no evidence for interaction between Tank 50H solids and uranium from the spiked salt solution. Lack of uranium removal may reflect prior removal of uranium. There is evidence for interaction between Tank 50H solids with plutonium and neptunium as evidenced by loss of these two actinides from the salt solution. The amount of plutonium and neptunium lost from solution increased with an increase in the quantity of Tank 50H solids for a fixed simulant volume. The removal of plutonium and neptunium fit typical sorption isotherms allowing development of loading curves for estimating maximum solids loading. The maximum loading capacities for plutonium and neptunium in the simulants are, respectively, 2.01 and 4.48 micrograms per gram of Tank 50H solids. The oxalate in the Tank 50H solids is not directly responsible for the loss of plutonium and neptunium from the salt solution. The removal of plutonium and neptunium may be attributed to other minor components of the Tank 50H solids. We recommend additional testing to identify the component responsible for the plutonium and neptunium removal.