The Determination of Total Plutonium in the Presence of Aluminum (open access)

The Determination of Total Plutonium in the Presence of Aluminum

Introduction: "The adoption of aluminum nitrate as salting agent in the Redox process made it imperative that a method be available for determining plutonium in the presence of aluminum. However, large amounts of aluminum have been found to interfere with the determination of plutonium by the lanthanum fluoride procedure. Previous attempts to increase the accuracy of the lanthanum fluoride method, by precipitating LaF3 from 4 M HF (rather than 2 M), have been successful only when the initial plutonium level was high."
Date: February 10, 1950
Creator: Burns, R. E. & Barton, G. B.
System: The UNT Digital Library
Production Test 235-5 Plant Process Evaluation Reduction of Plutonium Tetrafluoride With Calcium and Sulfur (open access)

Production Test 235-5 Plant Process Evaluation Reduction of Plutonium Tetrafluoride With Calcium and Sulfur

This report discusses the production of plutonium metal through the reduction of plutonium tetra fluoride with calcium metal and sulfur. It elaborates that iodine, which was originally used instead of calcium metal, presented several practical problems, but reductions completed with calcium were unsatisfactory.
Date: February 10, 1953
Creator: Kerr, W. B.
System: The UNT Digital Library
Preparation of Ductile Zirconium: Progress Report for January 1950 (open access)

Preparation of Ductile Zirconium: Progress Report for January 1950

Abstract: A new feeder chute on the continuous casting apparatus, and the use of outgassed zirconium chips resulted in a stable arc and quiet pool. Ingots up to 9 1/2 inches in length were made, and some correlation between tension on the ingot and the "necking" effect was determined. Conversions of zirconium iodide to zirconium in the arc dissociation apparatus ran from 41 to 48.2 percent with a maximum of 474 grams of metal produced in 4 hours.
Date: February 10, 1950
Creator: DiPietro, W. O.; Findlay, G. R. & Moore, J. H.
System: The UNT Digital Library
Concentration and Final Purification of Neptunium by Anion Exchange (open access)

Concentration and Final Purification of Neptunium by Anion Exchange

It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless steel corrosion products. The present specifications are for the neptunium final product to contain less than 0.1 weight percent plutonium, to be relatively free of gross metallic contaminates, and to be low enough in fission product game activity and Th234-Pa234 (UX1-UX2) beta activity to be handled without resorting to remote techniques.
Date: February 10, 1959
Creator: Ryan, J.L.
System: The UNT Digital Library
An Alpha, Beta, Gamma Transistorized Survey Meter (open access)

An Alpha, Beta, Gamma Transistorized Survey Meter

A portable, light weight transistorized alpha, beta, and gamma survey meter was designed and fabricated.
Date: February 10, 1956
Creator: Spear, W. G.
System: The UNT Digital Library