The tabulations on these pages include all of the known areas in Colorado, Utah, New Mexico, and Arizona having economically important uranium-vanadium deposits of the type which are generally referred to by the terms roscoe-lite and/or carnotite. Though similar deposits are known to exist in other areas they are to be viewed as being little more than mineralogical curiosities.

Technical report listing the errata for pages 2, 4, 5, 6, 7, and 8 for report CC-918.

Abstract. In the first section of this technical report a new method of extracting uranium from thorium nitrate solution is discussed. This method consists of extracting an aqueous solution of thorium nitrate, nitric acid, sodium sulphate, and potassium thiocyanate with hexone. By this procedure, using an equal volume of hexone it is possible to extract 83 percent of the uranium while only 0.3 percent of the thorium is extracted. other experiments show that even greater separations are possible. In the second section of this report the use of antipyrine in solvent extraction procedures is discussed. Experiments are described in which 90 percent of the uranium is extracted while the thorium is extracted to the order of 3 to 5 percent.

Partial abstract: "The investigation of the high temperature and pressure dissociation of water under irradiation was undertaken by the Power Pile Division of Oak Ridge National Laboratory in an effort to determine the degree of importance of the phenomenon with respect to the design of a high temperature water-cooled power reactor. Theory and past experimentation indicate that net steady-state dissociation is determined by the rates of the dissociation and recombination reactions under the imposed conditions, the dissociation rate being essentially a function of flux and the recombination rate essentially a function of temperature" (p. 3).

Abstract: "The analysis of hafnium and zirconium by the copper spark technique is presented for solutions of HCl, HF, and HClO4 acids. The special techniques of electrode protection and vacuum drying of perchloric acid samples are outlined. Also given are the working curves and deviations of both elements."

From introduction: "This is the first report on the study made of the possible power recovery without excessive cost, from the operation of the Brookhaven reactor."

Inroduction: "A study of the literature, particularly the work done by R. Strubl, I.W. Kolthoff and S.B. Smith, indicated that a polargraphic method for the estimation of T could be devised which would not sacrifice reasonable accuracy for rapidity. Work was begun with the intention of developing such a method."

Abstract: A summary of thermodynamic calculations for zirconium halides is given. Data indicates that the iodide is the most promising of the halides for arc dissociation and that good recoveries of zirconium should be obtainable provided dissociation is carried out at reduced pressure.

Summary: A set of conditions is described for a ten minute determination of water in TO₃ by ignition and absorption of the evolved water in magnesium perchlorate. Complete conversion to T₃O₃ is obtained under these conditions, so that total loss on ignition and total T (plus non-volatile impurity) content may also be obtained. It has been found unnecessary to employ Cu foil to prevent interference by nitrates, which may be present with a nitrate/water ratio as high as 5, and in an amount that does not exceed 100 mg.

"The experience at Oak Ridge National Laboratory in decontamination equipment and working areas from radioactivity has been summarized." The methods and reagents that were used for decontamination are discussed.

The flux standard is a device which will give a known flux-linkage change to be used as a calibration. At the Radiation Laboratory, two types of flux standards are used, a stationary type and a portable type.

Technical report. The object of the research is to determine the procedure and equipment for the preparation of U233 on a semi-works scale. The general proposed procedure is that thorium carbonate in aluminum cans will be irradiated with pile neutrons. The Pa233 resulting from neutron absorption the Th232 and the decay of Th233 will be extraction from 99% of the thorium and the natural U in thorium by MnO2 precipitations. The Pa233 will then be allowed to decay to U233 which in turn will be isolated from the remaining Th and partially decayed Pa233 by ether extraction.

Technical report with short reports on (1) Heavy water analysis and standardization, and Specific gravity of pure D2O; (2) Homogenous exponential experiment; (3) Recombination of pile gases; (4) Slurry pumping studies; and (5) Electron microscope laboratory.