Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

CHEMICAL TECHNOLOGY DIVISION, CHEMICAL DEVELOPMENT SECTION C MONTHLY PROGRESS REPORT FOR NOVEMBER 1959

Technical Report ·
OSTI ID:4172412
Bench-scale equipment and process for continuous stripping of uranium from di(2-ethylhexyl)phosphoric acid in kerosene with ammonium carbonate solution were demonstrated. Studies of corrosion and fission-product metal extraction from nitrate solutions with trilaurylamine are being conducted. Data on extraction of Mo, Zr, Sm, and Ru are discussed. Scouting experiments involving the use of di-sec-butyl phenylphosphonate and di(2-ethylhexyl)phosphoric acid for separation of contaminating thorium from Thorex U/sup 233/ are also examined. Reagent cleanup procedures were applied to severely degraded TBP--Amsco ststems, and it is noted that scrubbing the nitrated diluent with alumina appears to be the best method of removing hydrolysis products. Irradiation of organic process solvents such as tributylphosphate, di-n-butyl-phenylphosphonate, and di-sec- butyl phenylphosphonate is reported, and data on radiolytic production of organic acid are tabulated. Highly irradiated solvents could be cleaned up with Na/sub 2/ CO/sub 3/--Al/sub 2/O/sub 3/ solutions. Data on the formation constants for thorium sulfate complexes are also discussed. (J.R.D.)
Research Organization:
Oak Ridge National Lab., Tenn.
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-14-013777
OSTI ID:
4172412
Report Number(s):
CF-59-11-132
Country of Publication:
United States
Language:
English