Extraction of Uranium and Other Actinides From Nitric Acid by Di-N-Butyl N-Butylphosphonate (open access)

Extraction of Uranium and Other Actinides From Nitric Acid by Di-N-Butyl N-Butylphosphonate

From abstract: "Equilibrium data are presented for the distribution of uranium, other actinides, zirconium, and nitric acid between aqueous solutions and di-n-butyl n-butylphosphonate diluted with n-dodecane. Data for the physical properties and chemical stability of the phosphonate are also given."
Date: June 1957
Creator: Siddall, Thomas H., III & Loehlin, J. H.
System: The UNT Digital Library
Flow Characteristics of a Circular Weir in a Centrifugal Field (open access)

Flow Characteristics of a Circular Weir in a Centrifugal Field

Technical report outlining the use of circular weirs in solvent extraction between liquid phases of nuclear fuel elements. From Abstract : "A correlation of the experimental coefficients was developed to allow calculation of general weir performance."
Date: June 1961
Creator: Webster, Donald S.; Williamson, Clifton L. & Ward, James F.
System: The UNT Digital Library
The Nuclear Test Gauge (open access)

The Nuclear Test Gauge

From abstract: "The 'Nuclear Test Gauge', a slightly subcritical assembly for quality control of reactor components, was designed, constructed, and placed in operation. calibration experiments demonstrated that the sensitivity of the unit is adequate, and that the speed of testing is increased y a factor of ten over that of a critical test pile."
Date: June 1956
Creator: Parkinson, Thomas F.; Goosey, Malcolm H.; Heston, William M. & Hollberg, Herbert J.
System: The UNT Digital Library
Recovery of Plutonium From Metallurgical Reduction Residues (open access)

Recovery of Plutonium From Metallurgical Reduction Residues

Technical report. From Abstract : "A semicontinuous process was developed for dissolving the solid residues that are produced in the calcium reduction process for converting plutonium fluoride to plutonium metal. The slag and crucible residues are charged to a column-type dissolver, and are there exposed to a flowing solution of hot nitric acid followed by a nitric acid - aluminum nitrate solution. The resultant solution is suitable as feed for an ion exchange process for recovering plutonium."
Date: June 1961
Creator: Dukes, E. Kenneth & Prout, William E., 1921-
System: The UNT Digital Library
Scavenging of Ruthenium From Purex Uranyl Nitrate Solution (open access)

Scavenging of Ruthenium From Purex Uranyl Nitrate Solution

From introduction: "In previous work on the ion exchange adsorption of ruthenium, it was observed that when certain compounds of sulfur were added to dilute uranyl nitrate solutions, precipitates formed which carried ruthenium. The purpose of this investigation was to develop a similar method for scavenging ruthenium from concentrated uranyl nitrate solutions. Such a method, combined with the silica gel treatment for removing zirconium and niobium, might provide an integrated process to remove all three contaminants."
Date: June 1958
Creator: Prohaska, Charles A.
System: The UNT Digital Library