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Solvent extraction of irradiated neptunium targets. II. Flowsheet development

Technical Report ·
DOI:https://doi.org/10.2172/7318225· OSTI ID:7318225
Development of a solvent extraction flowsheet for processing /sup 237/Np and /sup 238/Pu at the Savannah River Plant as a possible replacement for anion exchange processing is described. The major difficulty in solvent extraction processing is maintaining neptunium in the extractable M(IV) or M(VI) valence states prior to extraction. Miniature mixer-settler tests with 7.5 vol percent TBP showed that a sidestream of ferrous sulfamate to reduce Np(V) to Np(IV) in the first bank of mixer-settler contactors greatly decreased loss of neptunium to waste. A nitrite sidestream to catalytically oxidize Np(V) to Np(VI) did not prevent high losses of neptunium.
Research Organization:
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
DOE Contract Number:
EY-76-C-02-0016
OSTI ID:
7318225
Report Number(s):
DP-1460
Country of Publication:
United States
Language:
English