Color changes and uranium deposits of the upper Morrison formation northeast flank of the Zuni uplift, New Mexico /

"January 5, 1955."

Uranium deposits in the Morrison Formation, Church Rock area McKinley County, New Mexico /

"May 1955."

An evaluation of Dynapak (HERF) extruded uranium tubes /

"AEC Contract No. AT-(30-1)-1405."

Mineralogy of uranium and thorium bearing minerals /

"RMO-563."

Recovery of uranium values from ore and concentrate samples : Colorado primary ores.

"United States Atomic Energy Commission Contract No. AT (49-6)-916."

Recovery of uranium from Chattanooga shale : final report.

Work performed by the Columbia University Mineral Beneficiation Laboratory under Contract AT(49-1)-621.

Recovery of uranium from Chattanooga shale; cost estimation of a solvent extraction plant, topical report.

"Contract No. AT(49-1)-621."

Recovery of uranium from Chattanooga shale : cost estimation of an ion exchange plant, topical report.

"Contract No. AT(49-1)-621."

The carbothermic reduction of uranium oxide /

Uranium oxide has been reduced by carbon under vacuum at 2250°C, to yield a product consisting of dendritic uranium carbide in a matrix of uranium.

Reactivity of certain uranium oxides with aluminum : terminal report /

"Contract No. AT-30-1 Gen-366."

Uranium dioxide fuel materials with improved thermal conductivity /

Work performed at the Sylvania-Corning Nuclear Corporation under contract AT (30-1) GEN-366 with the Division of Reactor Development.

Quantitative determination of uranium loading of aluminum-clad fuel plates by x-ray densitometry /

Work performed at the Sylvania-Corning Nuclear Corporation under Contract AT(30-1) GEN-366.

The enthalpy and heat capacity of uranium monocarbide to 1200C /

"Contract AT(30-1)-2789."

Volumetric analysis of uranium metal /

A precise and rapid method for the volumetric assay of uranium metal has been developed. The method consists of dissolving a weighed sample in an aqueous mixture of hydrochloric, sulfuric, and fluosilicic acids. The resulting uranium solution is titrated without a subsequent reduction step.

Investigation of salts for use in uranium metal heat-treating baths /

Numerous salts were considered for uranium metal annealing baths. Tests on melting point, solubility, corrosion stability, and hydrogen concentration were conducted on the salts which appeared to be the most feasible for this operation under existing conditions.